Regulatory Guide 5.9: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A205
| number = ML003740012
| issue date = 06/30/1973
| issue date = 12/31/1983
| title = Specifications for Ge(Li) Spectroscopy Systems for Materials Protection Measurements
| title = (Task SG 042-2), Revision 2, Guidelines for Germanium Spectroscopy Systems for Measurement of Special Nuclear Material
| author name =  
| author name =  
| author affiliation = US Atomic Energy Commission (AEC)
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-5.009
| document report number = RG-5.9 Rev 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 10
| page count = 8
}}
}}
{{#Wiki_filter:June 1973 U.S.!-ATOMIC ENERGY: COMMISSION
{{#Wiki_filter:Revision 2*
    0
                                                                                                                                      December 1983 U.S. NUCLEAR REGULATORY COMMISSION
                                  REGULATORY GtUUIDE
                        REGULATORY GUIDE
                                  DIRECTORATE OF REGULATORY STANDARDS
                        OFFICE OF NUCLEAR REGULATORY RESEARCH
                                                                    REGULATORY GUIDE 5.9 SPECIFICATIONS FOR Ge(Li) SPECTROSCOPY SYSTEMS
                                                            REGULATORY GUIDE 5.9 (Task SG 042-2)
                                            FOR MATERIAL PROTECTION MEASUREMENTS
                              GUIDELINES FOR GERMANIUM SPECTROSCOPY SYSTEMS
                                                    PART I: DATA ACQUISITION SYSTEMS
                                FOR MEASUREMENT OF SPECIAL NUCLEAR MATERIAL
                                                                              to boxes and cans of uncharacterized waste materia
 
====l. Meas ====


==A. INTRODUCTION==
==A. INTRODUCTION==
nuclear material forlims encounteled in the fulel cycle hoth for quantitative determintiont                        of the special Proposed revisions to section 70.51 ofl 0 CFR Part                          nuclear material cuntent, and for the determination of
urement conditions also vary widely from controlled laboratory environments to the unpredictable plant environ Section 70.51, "Material Balance, Inventory, and Records               ment that can be hostile to the measurement equipment Requirements," of 10 CFR Part 70, "Domestic Licensing                      and can often contribute serious background interferences of Special Nuclear Material," requires, in part, that licensees             to the spectral data. As a result, there is no single gamma authorized to possess at any one time more than one                         ray assay system that can be effective in all cases. The effective kilogram of special nuclear material establish and                system chosen for a particular NDA task must therefore be maintain a system of control and accountability so that                      determined from careful consideration of all factors that the standard error (estimator) of any inventory difference,                  may affect the measurement and of the requirements for ascertained as a result of a measured material balance,                      the precision and accuracy of the assay.
    70. "Material             Balwncc. Inventory and Records                         radionuclide abundances. In addition to the NDA of Requirenricnts." woold require licensees authorized to                           hulk materials, ganim:i ray spectroscopy is used in the possess at any one time more than one effective                                   analysis of specially prepared. homogeneous lahor:,lory kilogram  n.it" special nuclear material to establish and                         samples.
 
meets established minimum standards. The selection and proper application of an adequate measurement method for                        The scope of this guide is limited to the consideration of each of the material forms in the fuel cycle is essential for                high-resolution gamma ray spectroscopy with lithium-drifted the maintenance of these standards.                                         germanium, Ge(Li), or high-purity germanium, HPGe (also referred to as intrinsic germanium, IG), detectors. No Many types of nondestructive assay (NDA) measurements                    discussion of thallium-activated sodium iodide, NaI(Tl), or on special nuclear material (SNM) can involve, or even                      lithium-drifted silicon, Si(Li), gamma ray systems is
>  require, a high-resolution gamma ray spectroscopy system.                    presented. In addition, no discussion of specific NDA
  This guide is intended both to provide some general guide                    applications of gamma ray spectroscopy is provided. The lines acceptable to the NRC staff for the selection of such                  measurement procedures (including calibration), analysis systems and to point out useful resources for more detailed                  methods, Inherent limitations, and overall precision and information on their assembly, optimization, and use in                      accuracy attainable are specific to each application and are material protection measurements.                                            therefore the subject of separate application guides. Guide lines for measurement control, calibration, and error Any guidance in this document related to information                    analysis of NDA measurements are dealt with in detail in collection activities has been cleared under OMB Clearance                  Regulatory Guide 5.53, "Qualification, Calibration, and No. 3150-0009.                                                              Error Estimation Methods for Nondestructive Assay,"
                                                                                which endorses ANSI N15.20-1975,                  "Guide to Calibrating
                                                                                                                            1
 
==B. DISCUSSION==
Nondestructive Assay Systems." ANSI N15.20-1975 was reaffirmed in 1980.


maintain a system of control and accountability such that. the limit of error of any material unaccounted for                                  There is no single gainnna-ray spectroscupy system (UL1F): ascertained asa result of a measured mnaterial                            available which is satisfactory to r all a pplic ition s nor is halance, meets established minimum .standards. The                                there I standard which defines and specilies the typv or selection and proper application of an. adequate                                  types of Isstenls it) be used in cach of tihe above measurement method for each of the material forms in                               applications. T"his guide defines and details thle the fulccycle is essential for the maintenance of these                            specifications for ganmma ray spectroscopy dalta standards.                                                                        aquisition systems appropriate for special nuclear mnalcrial assay.
===1. BACKGROUND===
                                                                                    ýX of the major commercial vendors of Ge(Li) and Gamma ray spectroscopy systems are used for NDA of                       HPGe detectors and the associated electronics maintain various special nuclear material forms encountered in the                    up-to-date documentation on the specifications of currently nuclear fuel cycle, both for quantitative determination                      available equipment, as well as a variety of useful and infor of the SNM content and for the determination of radio                        mative notes on applications. This literature is available nuclide abundances.                                                              The substantial number of channes in this revision has made it Impractical to Indicate the changes with lines in the margin.


This is lhe. first in a two-part series of guides which present specifications for Iithium-drifted germanium.                                    The scope of this guide is limited to tht Ge(Li); gamma ray spectroscopy systems. This guidance                              consideration of Ge(Li) gamma ray spectroscopv applies to the .selection of.a special nuclear material                            systems; No discussion of thallitim-activa ted sodium (SNM) assay system which utilizes gamma ray                                        iodide. NaI(TI), gamma ray systems is presented. In spectroscopy for the quantitative delermination of the.                            addition. no discussion of applications of ganmma ray
the American Applications of high-resolution gamma ray spectroscopy                         Covpies of this standard may be obtained fromNew
                                                                                    1 Standards Institute, Inc., 1430 Broadway,            York, New have multiplied greatly in recent years. The samples encoun                National York  10018.


* SNM content and a qualitative detertuination of tile                                spectroscopy arc presnted. The nieasiremeit radionuclide abundances. Within each of the, guides in                            procedures (including calibration), analysis nelthods.
tered range from fresh fuel rods and reprocessing solutions Comments should be sentCommissionto the Secretary      of the Commission.


this series, Data Acquisition and Data Reduction.                                 inherent limitations, and overall precision and accuracy I variations of a basic spectroscopy system are defired and                            are specific to each application and are therelbre the individual specifications provided. The procedures for                            subject of separate application guides.
USNRC REGULATORY GUIDES                                    U.S. Nuclear Regulatory                        Washington, D.C. 20555.


applying these systems to specific materials and the analysis of the reduced data is tile subject of a later                                    An elementary introduclion to the concepis
make available to the        Attention: Docketing and Service Brancn.
. guide.                                                                              associated with the application of G;etLU spectroscopy to problems of nuclear material assay is available.'


==B. DISCUSSION==
Regulatory Guides are Issued to describe andstaff    of implementing public methods acceptable to the NRC                to delineate tech-      The guides are Issued In the following ten broad divisions:
Descriptions of the physical processes of gamma ray detection, discussiotIs of important instrumenlalion I. Background L. A. Kull, '.'An Introduction to (;C('Li) Uitsd Nal GammaIray spectroscopy systems have been used                                Garnma-Ray            Derectorz ror Safeiiuard% Applicauiiomu."
  specific parts of the Commission's    regulations, niques used by the staff in evaluating specific problems or postu            1. Power Reactors                      6. Products Regulatory iated  accidents or to provide guidance to applicants.               with    2. Research and Test Reactors            7. Transportation Guides are nof substitutes for regulations, and compliance from  those set    3. Fuels and Materials    Facilities    S. Occupational Health them Is not required. Methods  and  solutions different                                                              9. Antitrust and Financial Review
  for the nondestructive assay (NDA) of various special                              ANL.AECA-103 (1973).
                                                                                4. Environmental and Siting out in the guides will be acceptable If they provide of a permit the a basis  for or    5. Materials  and  Plant Protection    10.  General findings requisite to the issuance or continuance license by the Commission.                                                   Copies of issued  guides may   be purchased  at the current Government Printing Office price. A subscription service for future      guides in spe This guide was Issued after consideration of comments received      from                                                    Government    Printing Office.
                        USAEC REGULATORY GUIDES                                      Copies of published quides may be obtained by request indicating the divisions deIlred to the U.S. Atomic Energy Commission, Washington, D.C, 20545, Regulatory G ures.ae issued to describe and make avIiiablato the public           Attention: DIrctot, of Regulatory Stendards. Comments and suggestions lot methods acceptable to the AEC. Regulatory staff of Imp*iamen5'ng specific parts Of Imptrovements in these guides are encouraged and should be sent to the Secretary the Commilsio"'$ regulations, to .de*tnea*s techniques used by. the naff In       of the Commission. 1U. Atomic Energy Commission, Washington. D.C. 20545, evaluating specIssc.probIems or poetuiatad accidents, or toprovtide guidance.to   Attention: Chlef.PubltcPtoceedingsStaff.
 
in these    cific divisions   is available through    the the public. Comments and suggestions for Improvements will  be revised,  as    Information on the subscription service and current        GPO  prices may guides are encouraged at all times, and guides                                be obtained by writing the U.S. Nuclear RegulatorySales       Commission, appropriate, to accommodate comments and to reflect new informa-              Washington, D.C. 20555, Attention: Publications                    Manager.
 
tion or experience.
 
from the manufacturers upon request, and the potential                an integral part of the detector package. The preamplifier customer may use this literature as a source of the most signal is further amplified and shaped and is then converted current information on the highest quality systems available.
 
into digital information that can be stored, displayed, and otherwise processed by the data reduction and analytical Finally, the potential user ought to consult with those            components of the system.


compliance applicents. Regutato*y Guides are not subtiltules fat regulations and with them is not requited. Methods andrsolutions dilferent from those set out in  The guides areIssued in the following ten broad divis!ons:
individuals currently active in the field of nondestructive assay of special nuclear material and seek their advice in the        
  the ipides will be acceptable it they providea bels'fot the findings reqiuisita to the issuance or continuance of a permit.ot license by thecCommisionI'.              L Poesre R    ReacTrtors                   


===6. Products===
===4. TYPES OF SYSTEMS===
                                                                                      2.'Resorch end Test neactots              7.. Teerssportetiors
  particular assay problem being considered.
                                                                                      3."  Fuels and Materlels Facilities        B OccuPational Health Published guides will be revispe periodically. as appropriate. to ea-ommodate      4. Environmental end Siting                9. Antitrust Review cosm entI* nd to reflect new inlermatlon or experience.                            5. Materials and Plant Protection        1


===0. General===
High-resolution gamma ray spectroscopy systems are
  2. BIBLIOGRAPHIC INFORMATION                                            distinguished primarily by the type (p-type or n-type) and the configuration (planar or coaxial) of detector used. For An annotated bibliography is included in this regulatory assay applications involving the measurement of low-energy guide to provide more detailed information on spectros gamma radiation (i.e., energies below approximately copy systems and their use.                                            200 keV), a thin planar HPGe or Ge(Li) crystal is most appropriate. A coaxial detector crystal with a larger volume Elementary introductions to the concepts associated                is much better suited for higher energy gamma ray measure with the application of high-resolution gamma ray spectros            ments (i.e., for energies above approximately 120 keV).
  copy to problems of nuclear material assay are available in            The distinction between these two types of detectors is not Augustson and Reilly and in Kull. These works discuss                  sharp. For instance, there maý be some applications above the physical processes of gamma ray detection and impor                120 keV in which a planar detector would be useful to tant instrumentation characteristics. More advanced dis                render the system less sensitive to interferences from cussion of gamma ray detectors and associated electronics ambient high-energy gamma radiation.


characteristics, and a step-by.step description of~a simple                assay. work. The system is designed to measure gamnnma assay problern.are. included in this document. Relevant                    rays with energies greater than 120 keV.
may be found in Knoll and in Adams and Dams. A thorough treatise on the associated electronics is available in Nicholson.


*"information.presented :at a 'somewiat higher' technical                      I!. A moderate to high efficiency system which level. including nomenclature and definitions. is                         can. satisfy all 'ihe requisites for System I and whirh. in inmiained in two useful standards documentls.2 - These                    addition, hasthe improved energy resolution necessary des. ribe .detailed techmiques for defining and..obtaining                to.assay for the pltitonitmni isotopes 238 through 241.
It should be noted that Ge(Li) detectors have no real In addition, extensive discussion of a variety of NDA tech advantage over HPGe detectors with comparable perform niques and the implementation of some of these techniques              ance specifications. In addition, Ge(Li) detectors require with high-resolution gamma ray spectroscopy may be                      constant liquid nitrogen (LN) cooling, even when not in found in Sher and Untermeyer, in Rogers, and in Reilly and              operation. HPGe detectors are, of course, also operated at Parker. Detailed descriptions of detector efficiency and                LN temperature, but they can be stored at room tempera energy calibration procedures are available in section D of            ture. This is an advantage to potential users who may have Knoll and also in Hajnal and Klusek; in Hansen, McGeorge,              extended plant shutdowns. It also prevents complete loss and Fink; in Hansen et aL; and in Roney and Seale.                    of a detector due to operator procedure error, which can happen with a Ge(Li) detector when Ll4 cooling is not Relevant technical information beyond the introductory level, including nomenclature and definitions, is contained continuously maintained. This added convenience and the greater ruggedness of the HPGe detectors make them K
  in three useful standards of the Institute of Electrical and especially attractive for in-plant NDA applications.


meaningful peirormance data for Ge(Li) detectors and                    .This system is commonly used to determine tile relative amplifiers. The glossary of technicalmterns found in both                  radionuclide abundances and is designed to measure
Electronics Engineers, ANSI/IEEE Std 301-1976, "Test Procedures for Amplifiers and Preamplifiers for Semi                  5. EQUIPMENT ACCEPTANCE PRACTICES
              [ohese standards documents will priwve valuable to those                  gamma rays with energies greater than 120 keV.
  conductor Radiation Detectors for Ionizing Radiation," 2 ANSI/IEEE Std 325-1971, "Test Procedures for Germanium Equipment descriptions and instructional material Gamma-Ray Detectors" 2 (reaffirmed in 1977), and ANSI/
                                                                        covering operation, maintenance, and: servicing of all IEEE Std 645-1977, "Test Procedures for Hifh-Purity                     electronic components are supplied by the manufacturer Germanium Detectors for Ionizing Radiation,"" which for all individual modules or complete systems. Such supplements ANSI/IEEE Std 325-1971. These describe                      descriptions should include complete and accurate sche detailed techniques for defining and obtaining meaningful matic diagrams for possible in-house equipment servicing.


" *Unfamiliar.it I gamma-ray. spectrosc pic nomenclature.                      Ill..A. system. designeUl specifically for low-energy gamma ray..and X-ray 'spectroscopy (at gamma ray Finall,..there :is a coiisiderable :amouit Of valuable            energies less than 200 kcV) having an energy resolution backgroundmnaterial published by he. manufacturers of                      adequate to perform quantitative and qualitative.assays detectors'aid associated 'electronic hardware which is                     of specially . prepared samples for the isotopes of available. fro ithemnon request.                                            plutonium (238-241) and uranium (235 and 238).
performance data for Ge(Li) and HPGe detectors and                     Complete operational tests of system performance are to be amplifiers.                                                           made at the vendor's facility, and the original data are
              2. Functional Description                                                  4. Equipment Acceptance Practices A.block diagram of those components of the Ge Li)                        Standard practices regarding the final acceptance of spcctroscopy system which perform the data acquisition                    equipment arc ustially prescribed by individual
                                                              /
              *funlction in material protection measurements is shown                  companies. laboratories, or departments. However. some S"        in Fig. I. lhe function of these components is first to                    of the following procedures have. beens found to be convert the charge produced by the interaction of an                        useful in providing the user with the assurance that he incident irmma ray with the Ge(Li)-delector into an                        will acquire equipment which will perform as expected amplified. analog electrical signal. The analog signal is                    in nuclear materialassay applications.
                                                                        supplied to the user upon delivery of the equipment.


then converted into digilal information which can be stored, displayed, and otherwise processed by                                     Equipment descriptions .(including tile theory of appropriate data reduction and analytical modules.                           operation) and instructional material covering operation.
3. FUNCTIONAL DESCRIPTION                                              Extensive performance testing of all systems by the user is generally not necessary. 3 However, qualitative verification A block diagram of a typical high-resolution gamma ray            of selected equipment performance specifications and spectroscopy system is shown in Figure 1. In such a system,            detector resolution is recommended.


maintenamce. and servicing of all electronic components
the solid state Ge(Li) or HPGe detector converts some or all of the incident gamma ray energy into a proportional It is necessary to have calibration sources on hand to amount of electric charge, which can be analyzed by the                verify the operational capabilities of the system. The subsequent electronics. The detector output is converted following radioactive sources (with appropriate activities)
            3. Types of Systems                                                          should be supplied for individual components or complete systems. Such descriptions should include There are three variations of the basic data                        complete and accurate schematic diagrams for possible acquisition system presented in this guideline. This                        in-house equipment servicin
into an analog voltage signal by the preamplifier, which is
                                                                            3 Although the quality control and presh.pment testing may be obtained from the Institute of Electrical and      dures of the commercial vendors of detectors and associatedproce.elec.


====g. Carefully specified====
Electronics Engineers, Inc., 34S East 47th Street, New York, New          onuic, h~ave improved and are quite dependable, some user verifica.
        *    variance in the basic configuration is the result -of                      operational tests of system performance should be made attempts to optimize each system to obtain specific                        at the vendor's'facility and the original data supplied to assay information from certain types of material forms.                      the- user before equipment delivery is scheduled, with final acceptance based. on the user's own performance The. three ..variations -of the basic system are                      data taken at the user's facility.


'        described below' and will be referred to by' Ronan numeral in the remain der of the document. (For                                  It is necessary to have calibration sources on hand example. System II refers to paragraph II below.)                            to verify the operational capabilities of the system. The
York 10017.                                                             tion of the specifications claimed by the manufacturer Is strongly recommended.
                    1. A' moderate to high efficiency system having an                  following radioactive sources (with appropriate
  *.        energy resolution which is adequate for assays of                            activities) will provide sufficient counting rates to materials for the fissile isotopes 2 4 'Pu, 2 3 9 Pu, 235 U.                perform the tests specified in the regulatory position:
  *          and 2 -13U. it can also be used to perform assays of                              "0 Co- 10.30 MCi


* materials for fertile isotopes such as 2"1 Th and 2"%BU                            ,',co-1-10o Ci and to determine tile "ag" of plutonium samples from
5.9-2


* measurements of their americium-241 conten
I                        I
      I                \      I
      I                        I
          I    Uquld          I
              Nitrogen                              High Dewa                          Voltage I      (Cooling)                            Supply                                Spectrum f        .Stabilization I
                                                              Spectroscopy      I        Analog-to-Digital I          Detector            Preamplifier              Amplifier                  Conversion                II
      I
        I.                                              I                                          ,                    I
                                                        II
                                                                Count                                                  I
                                                                  Rate Scaler              Data storage, display, and data reduction and analysis      I
                                                                                            components                I
                                                                                      I                              I
                                                          FIGURE 1 A block diagram of a typical setup of a high-resolution gamma ray spectroscopy system. The dashed boxes indicate which sets of modules are usually packaged as one component in commercially available systems. Liquid nitrogen cooling of the detector is required for proper operation of the system, but the field-effect transistor (FET) in the preamplifier input stage may or may not be cooled, depending upon the type of detector used and the energy resolution desired. A scaler is shown connected to the main amplifier, a common method of monitoring the total system count rate. For long-term data acquisi tion, spectrum stabilization is recommended, and the method is indicated here by a stabilizer module in communication with the analog-to-digital converter (ADC).
                                                              5.9-3


====t. This====
will provide sufficient counting rates to verify the energy                will always have LN-cooled FET preamplifiers in order to resolution specifications of the manufacturer and to carry                  achieve the excellent resolution of these systems. The out any other performance tests desired by the user:                        preamplifier feedback loop may be either pulsed optical or resistive, 7 and the system will have fairly modest rate
       *      system is used in those applications where Nal resolution                                 
       60Co 10-30 pCi, Gamma ray energies: 1173,1332 keV
      57                                                                      capabilities in the range of 5000 MeV/sec. 6 It is important CO 1-10 j0i, Gamma ray energies: 14, 122, 136 keV
                                                                              to decouple the detector from noisy mechanical environ ments to avoid microphonic pickup.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
is inadequate to accurately resolve the gamma ray lines of the isotopes of interest from those from an interfering                        Lithium-drifted germanium, Ge(Li), gamma ray
2. ELECTRONICS PERFORMANCE
*        " background. and where the lower efficiency Ge(Li)                           spectroscopy data acquisition systems meeting the detector still provides sufficient sensitivity for practical               operating specifications given below are considered adequate for use in special nuclear materials assay. The
      Ge(Li) or HPGe gamma ray spectroscopy data acquisi tion systems meeting the general guidelines outlined briefly                  For ease of use, maintenance, and replacement of the below are considered more than adequate for use in SNM                      components in a high-resolution gamma ray spectroscopy assay requiring resolution better than that obtainable with                system, the electronic components should be standard Na! detectors. The potential user should select the detector                nuclear instrument modules (NIM) (Ref. 1), with the and associated electronics that meet the needs of the partic                possible exception of the pulse-height analysis (Le., multi ular assay task required, with careful consideration of all                channel analyzer) components. Pulse signals should be factors that could affect the quality of the assay.                        transmitted from module to module in shielded coaxial cable to minimize the effects of possible electronic noise
                     `-Te-t Procedure for Amplifiers and Preamplificrs far                selection of a system meeting these specifications is Semiconductor Radiation        IDoectors.' IEET Std 3011-969. The          considered necessary but not suflicient for accurate Institute of Electrical and Electronics Engineers. Inc. (1969).           gamma ray spectroscopic assay requiring resolution better than obtainable with Nal, No guarantee of
  1. DETECTOR PERFORMANCE                                                    from nearby machinery at the measurement site. The cables should have a characteristic impedance that matches the Excellent performance, routinely available in coaxial                  terminations used in the NIM modules (generally 93 ohms).
                    '"Tesi Procedures for Germanium Gamma-Ray Detectors.'.
germanium detectors, may be represented by energy resolutions (FWHM) 4 of approximately 1.7 keV at 1332 keV                      The system power supplies (detector high voltage,
              IE-EE Sid 325-1971. 'nt:e Institute cif 'leciricil and ElectronlcN          measurement quality as a result of the application of Engineers. Inc, (1971).                                                     such. systems should be assumed.
( 60 Co) and approximately 0.7 keV at 122 keV ( 5 Co) for                  preamplifier, and NIM bin) should be capable of operating detectors with efficiencies up to 20 percent. 5 The full width              the system within the operating specifications when supplied at 0.1 maximum (FWTM) for such detectors is typically up                    with 115 volts (+10 percent) at 50 to 65 hertz (at constant to 1.9 times the FWHM. For these higher efficiency detec                    room temperature). The power supplied for the detection tors, "peak-to-Compton ratios" are usually quoted in the                    system should be stabilized against voltage shifts in order to range of 25 to 40. These ratios are strong functions of                    maintain resolution. The output voltage of the detector bias resolution, efficiency, and exact detector crystal geometry,               supply is determined by the detector requirements; 5 kilo and no typical values can be given without knowledge of all                volts is sufficient for most applications.
 
of these parameters. Coaxial detectors with this kind of resolution will usually have cooled field-effect transistor                     The main amplifier, commonly referred to as the spectros (FET) preamplifiers and an energy-rate capability of                      copy amplifier, should have variable gain and pulse-shaping approximately 50,000 MeV/sec. 6 Room temperature pre                      controls for maximum setup flexibility. Most high-quality amplifiers have somewhat worse resolution but have rate                    amplifiers are equipped with baseline restoration and capabilities on the order of 150,000 MeV/sec.                              pole-zero cancellation circuits (Ref. 2), which greatly improve the resolution that can be achieved on a routine The resolution of planar detectors is a stronger function              basis. Baseline restoration is essential for assay situations in of the crystal size and shape than that of coaxial detectors,              which count rates in excess of several kilohertz are antici so representative resolutions cannot be given over a range of              pated. Pulse pileup suppression is also a useful feature, if sizes. As an example from the middle of the range of sizes                available; it may be found in some spectroscopy amplifiers usually offered, an excellent 2 cm 3 planar detector (le.,                and even in separate NIM modules designed for that purpose.
 
2 cm 2 front face area x 1 cm thick) would have a resolution of approximately 0.5 keV at 122 keV (5 7 Co) and 0.21 keV                      Electronic components should be obtained with state-of at 5.9 keV (Mn X-ray from SaFe decay). Planar detectors                    the-art linearity and temperature sensitivit
 
====y. Maintenance====
    4 The full width of the gamma ray photopeak at half of its              of long-term gain stability may require the use of a spec maximum height (FWHM) is defined in ANSI/IEEE Std 301-1976.                trum stabilizer. Centroid variations of a stabilization peak SThe full-energy peak efficiency (in percent) is defined relative      of less than one channel in a 4096-channel spectrum are to the full-energy peak efficiency of a 3-in. J.n. NaI(TI) scintilla        achievable with commercially available stabilizer modules.
 
tion detector for 1332-keV gamma rays v Co) at a source-to.                 Stabilization peaks can be provided either by a pulser or by detector distance of 25 cm. The detailed procedures for determining the efficiency in accordance with this definition are presented in          a radioactive source. Generally, a radioactive source is Section 5.2 of ANSI/IEEE Std 301-1976.
 
preferred because it contributes less distortion to the
    6 Counting rate capabilities, expressed In MSV/sec, denote the          gamma ray spectrum and has a stable (although decaying)
maximum charge-to-voltay. conversion rate of which the pre                  emission rate. Furthermore, stabilization peaks from amplifier Is capable. For " Co, a SO,000-MeV/sec rate capability corresponds to a pulse iunting rate limitation of approximately            natural sources may be obtained from existing peaks
80,000 counts/sec. For Co a 000-MeV/sec rate capability also                in the assay spectrum itself, which simplifies the assay corresponds to a pulse rate limitation of approximately 80,000
counts/sec. Of course, nuclear material assays should be performed at count rates well below these limiting values in order to minimize            7 Feedback methods for charge-sensithve preamplifiers are dis rate-related losses from pulse pileup and dead time.                       cussed thoroughly in Chapter 5 of Reference 2.
 
K\
                                                                      5.9-4


I"                                                                          .. .*",:5.9-2'
on the sensitivity, precision, and accuracy of any assay. The setup. Dead-time and pileup corrections may also be              range of gamma ray energies of interest also determines the performed using a pulser or a separate radioactive source        type of gamma ray detector appropriate for optimum fixed to the detector. The latter method is preferred for the    efficiency.


characteristics, and a stcp-by-step description of a.simple                assay work. The system is designed to nmeasure gatnma assay problem are. included in this.document. Relevant                    rays with energies greater than 120 keV.
reasons stated above.


hi 'ormation
b. Full-Energy Peak Area Determination: The proce
        .             presented at a somewhatt higher technical.                    II. A moderate to high efficiency system which level. including nomenclature and definitions, is.                        can satisfy all the requisites for Systen I and which. in contained. in two useful standards documents. 2 . These                    addition, has thc imiproved energy resolution necessary de,;cribedetailed techniques for defining and obtaining                    to assay. for tile plttoniuim isotopes 238 through 241.
3. SYSTEM SELECTION AND USE                                      dure for extracting this fundamental information from the spectral data will be determined by the complexity of the The detailed requirements and constraints of a particular    gamma ray spectra as well as the intensity and complexity measurement situation will cause wide variation in the            of the gamma ray background at energies near the peaks of optimum choice of systems, even within a fairly well-defined      interest.


" tmeaningful perfornmance data for Ge Li) detectors:and                   This system is commonly used to determine the relative aplifiers.
application. For example, a requirement for high through put may dictate higher efficiency detectors and highly                c. Gamma Ray Attenuation by the Samples and Sur automated data acquisition electronics. Anticipated inter        rounding Materials: Corrections for this effect are essential ferences from uranium, thorium, or fission products may          for accurate assays. The importance of this correction will make the best possible system resolution the most impor          increase as the gamma ray energies of interest decrease and tant consideration. Severe operating environments may            the absorptive power of the sample and surrounding mate make the use of digital stabilization highly desirable. Con      rials increases.


n*            The. glossayv o0f.technical terms found in both          radionuclide abundances and is designed to measure
straints of space and location could dictate an unusually small LN dewar with automatic filling capacity. The list of such considerations in a given situation can be long, and          All of this emphasizes that by far the most important each situation should be considered carefully and indi            factor in choosing an appropriate data acquisition system, vidually in order to achieve a system that can acquire the        in Implementing proper assay procedures, and in supervising required measurement data.                                       the assay operations is a highly competent person, prefera bly experienced in gamma ray spectroscopy and its appli Beyond the choice of data acquisition systems, many            cation to assay measurements of special nuclear materials.
  , these..standards docuiments Will prove valuable to those                  gamma rays with energies greater than 120 keV.


"ounfamiliar with camnia-rtvy spectroscopic nomenclature.                      Ill. A system designed specilically for low-energy gamma ray and X-ray spectroscopy (at gamma ray Finally. there is a considerable amnount of valuable              energies less than 200 keV) having an energy resolution
other factors influence the successful use of gamma ray           Such a person, with the assistance of the existing literature spectroscopy in quantitative assay measurements. Some of         and of others in the gamma ray field, will be able to consid these are:                                                        er a particular application in detail and choose an appro priate detector and electronics to create a data acquisition a. Gamma Ray Signatures: The energies and intensities          system that is well suited to the required assay task.
  .background material published by tile inanufacturers of                    adequate to perform quantitative and qualitative assays detectors and associated electronic hardware which is                      of specially prepared samples for the isotopes of available from them on request.                                            plutonium (238-241) and uranium (235 and 238).
  2. Functional Description                                                  4. Equipment Acceptance Practices A block diagram of those components of the Ge( Li)                        Standard practices regarding the final acceptance of
  *spectroscopy system which perform the data acquisition                    equipment are usually prescribed by individual function in .material protection measuremenis is shown                    companies. laboratories, or departments. However. some in Fig. .I. The function of these components is first to                  of the following procedures have beet, found to be convert the charge produced by the interaction of an                       useful in providing the user with the assurance that lie incident aninma ray wvith the Ge(Li) detector into an                      will acquire equipment which will perform as expected amplified, analog electrical signal. The analog signal is                   in nuclear material assay.applications.


then 'convertcd into digital information which can be stored., displayed, and otherwise processed by                                    Equipment .descriptions (including the theory of appropriate data reduction and analytical modules.                          operation) and instructional material covering operation.
of the relevant gamma rays place fundamental restrictions
                                                              5.9-5


maintenance, and servicing of all electronic components
REFERENCES
  3. Types of Systems                                                        should be supplied .for individual components or complete systems. Such descriptions :should include There are, three -variations of the basic data                    complete and accurate schematic diagrams for possible acquisition system presnted, in this guideline. :This                      in-house, equipment servicing.. Carefully specified variance in thc basic configuration is tile result of                      operational tests of system performance should be made attempts to optimize each system to obtain specific                        at the vendor's facility and the original data supplied to assay information from certain types of material forms.                      the user before equipment delivery is scheduled, with fimal, acceptance based on the user's own performance The three variations of the basic system arc                        data taken at the user's facility.
  1. L Costrell, "Standard Nuclear Instrument Modules,"
                                                                  2. P. W. Nicholson, Nuclear Electronics, John Wiley and U.S. Atomic Energy Commission, TID.20893, Revi Sons, New York, 1974.


described below and will be referred to by Roman numeral in the remainder of tile document. (For                                  It is necessary to have calibration sources on hand example, System 11refers to paragraph 11below.)                              to verify the operational capabilities of thie system. The
sion 3, 1969.
      *I. A moderate to high efficiency system having an                    *following radioactive sources (with appropriate
*  energy resolution which is adequate for assays of                          activities) will. provide sufficient counting rates to materials for the fissile isotopes 24,Pu, 239pu, 2.15U.                    perform the tests specified in the regulatory position:
  and 2 13U. It can also be used to perform assays of                              6 OCo- 10-30 /Ci materials for fertile isotopes such as 23 2Th and 2 3 1U                          I 7 Co-I-10upCi and to determine the -age" orplutoniunt samples from measurements of their americium-241 content. This system is used in those applications where Nal resolution                                 


==C. REGULATORY POSITION==
BIBLIOGRAPHY
is inadequate to accurately resolve the gamma ray lines of the isotopes of interest from those from an interfering                        Lithium-drifted germanium, Gc(Li), gamma ray background and where the lower efficiency Ge(Li)                          spectroscopy      data acquisition systems meeting the detector still provides sufficient sensitivity for practical              operating specifications given below are considered adequate for use in special nuclear materials assay. The
  Adams, F., and R. Dams, Applied Gamma-Ray Spectros                  This is an extensive treatise on electronics systems copy, Pergamon Press, New York, 1970.
          "*'"lest Procedure. for. Amplificr.ý and Preamplifiers for        selection of a system meeting these specifications, is Serniconductor Radiatinn IDteetors'" IEE:. Std 301-1969. The                considered. necessary but. not sufficient for accurate Institute of Eteetricat and -leCtronies Engineers. Inc. (19691."          gamma ray spectroscopic. assay requiring resolitilion better than obtainable :with Nal. No. guarantee, of
 
          *"Test Prncedurcs for Gernmniurn Ga"niaýRay De"tectors.-
associated with high-resolution detectors.       Detailed descriptions are given of detector preamplifiers, pulse This work provides a comprehensive coverage of back shaping, rate-related losses, pulse-height analysis, and ground material pertinent to the gamma ray spectros spectral resolution.
  IF-.'    Std 325-1.971. Tlhe Institute nlr Electrical and Electrunics      measurement quality as a result of the application of Engineers. Inc. (1971).                                                    such sys!ems should be assumed.
 
copist. Considerable information is provided on both Nal and Ge detectors.                                       Reilly, T. D., and J. L Parker, "Guide to Gamma-Ray Assay for Nuclear Material Accountability," Los Alamos Augustson, R. H., and T. D. Reilly, "Fundamentals of Scientific Laboratory, LA-5794-M, 1975.


5.92
Passive Nondestructive Assay of Fissionable Material," Los Alamos Scientific Laboratory, LA-565 I-M, 1974.


".Q'" i The .enipho %ishere ison the 1perating specifications            the. spectrutm lpeaks of interest in a reasonahle period of related to the overall performance off tile entire .data                  time.      Est intates should be corrected for.
This report briefly covers the principles involved in using gamma ray spectroscopy in the quantitative assay of This manual contains helpful introductory descriptions SNM and attempts to describe both capabilities and of NDA applications of gamma ray spectroscopy, as well limitations of gamma ray assay techniques. The report as some discussion of gamma ray detection systems.


* acquisition system. Component specilicat ions have~been                  sample-to-detector distance and tlie effects of absorbing included in Appendix A to provide guidance in the                      materials placed between tile sample and detector.
also includes a description of procedures for determining Hajnal, F., and C. Klusek, "Semi-Empirical Efficiency                plutonium isotopic ratios.


selectiol,; of original Or replacenten I co1Iponen S which              Whenever possible. it. is advisable Ito make preliminary are essential if adequate system performance is to be                    measurements oin tile samples under consideralion with
Equations for Ge(Li) Detectors," Nuclear Instruments and Methods, Vol. 122, p. 559, 1974.


* attained. The system operating performance s,,hould not                an available detector, and the efficiency of t(ie optimal be deduced from the component performances: overall                      deleclor determined by extrapolating the meastred system performance should be checked independently                      results. A Ilumni:al estilalte of the detector.efficicncy (..Is and compared to tile operating specifications presented                  defined above) required for most applications, is here.                                                                   approximately 8%1: however, detectors with elficiencies a ithe rang of 5 " o 20.,   _ are ill use For nuclear material
Rogers, D. R., "Handbook of Nuclear Safeguards Measure ment Methods," Nuclear Regulatory Commission, NUREG/
              1. Energy Resolution and Peak Shape                                    assays. (To assist in providing some perspective here. an
Hansen, J., J. McGeorge, and R. Fink, "Efficiency Calibra CR-2078, 1983.
                                                                                    8%,`detector as speciflied above has an active volumnL of (Systems 1, 11, 111) The eniergy resolution of the              about 40 cc while 5 to 207, detectors have voltmes of
            .system should be measured according to the procedure                    about 25 cc to 110 cc. respectively. Art , detector has
                                                                                                                                              4


* specified in IEEE Standard 325-197i,4 with the                          absolute detection efficiencies of about 15 x .1"T              185 following additional stipulations: (I) the peaking time"               keV, 4.5 x 10-4 (a: 411 keV. and 0.96 x 10" . (a 1.33 for the shaping amplifier should be no. greater than 4                  MeV at a source-detector sepai:itionrof 25 cm.)
tion of Semiconductor Detectors in the X-Ray Region,"
            .pseec (2) the total number of counts in tthe Ltnter channel of the peak should be no less than 104 counts;                        (Systemn i11) The method described above for
Nuclear Instruments and Methods, Vol. 112, p. 239, 1973.
            (3) the count rate during the measurement should be in                  determining the detection efficiency witlh a high energy the range 102 to 10-1 counts per second as measured                    gamma ray source is not relevant for detectors used in with a total count rate meter. The full width of the peak                low-energy gamma ray spectroscopy. Instead. it is more at half maximum (FWHM) and full width at                                appropriate to specify. (I) the active volume of the tenth-maximum (FWTM) are as defined in IEEE                            detector and (2) the maximum effect of absorbing Standard 325-1971.6 The full width at 1/50 maximum                      materials (absorbing materials include detector surfacc (FW.02M) is defined in a similar manner. The energy                      "dead layers," gold surface plating, and the end cap resolution and peak shape specifications for each of the                window of the cryostat). The following specifications systems (I i1, 111)are given in Table I and the measured                are therefore given for the low-energy gamma ray
            .values should be no greater than those shown here.                      system:
            These values have been determined to be necessaryfor                          a. detector volume- 1.0 to 1.5 cc theapplications defined in B.3. above.                                        b. drift depletion depth--0.5 to 0;7 cm c. layers of absorbing material between the
            2. Detection Efficiency                                                  radiation source and the active volume of the detector must be thin enough so that the 14.4 keV peak from a (Systems 1, 11) The full energy peak efficiency (in              s 7Co source is at least 5 times the conlitiltuin percent) is defined relative to the full energy peak                    background under the peak."
            efficiency of a 3 in. x 3 in. Nal(TI) scintillation detector for 1.33 MeV gamma rays ( 6 'Co) at a source.detector                    3. Count Rate Capabilities distance of 25.0 cm. The detailed procedures for determining the. efficiency in accordance with this                            The following specifications are related to a definitionare presented in IEEE Standard 325.1971.L                    system's ability to maintain adequate energy resolution at high co.unt rates.


Tile efficiency required for specific assay applications should be determined .by estimating the                          (Systems I. 11) The system should be capable of gamma ray intensity at the detector from a sample of                    o0ratingvat a" total counting rate of: 104 cps from a known...strength and the counting rates required to                        Co source (as measuredwith a total count rate meter)
Chapter 5, "Passive Nondestructive Assay Methods,"
            collect a statistically significant number of counts under              with less than a 10% i,-,lative increase in.the 1.33 MeV
Hansen, J., et al., "Accurate Efficiency Calibration and contains descriptions of many applications of high          K
                                                                                      peak width at 1/10 the maximum peak height (,VTMý
                                                                    resolution gamma ray spectroscopy, as well as many Properties of Semiconductor Detectors for Low-Energy references to original papers and reports.
                  S'IEEE Sid 325-1971, op. cit.. Srction 4.                          as compared to the FWTM value measured at 102 ito 10:
                                                                                      cps.


'Peaking time-the time required for a pulse to reach its maximum height. Peaking times can be easily measured with an                  (System Ill) The system should be capable of oscilloscope and are less susceptible to misinterpretation than arc    operating at a total counting rate of 5 x 103 cps fiomi a RC time constants. The relationship between RC time constants          s Co source (as measured with it total count rate ittler)
Photons," Nuclear Instruments and Methods, Vol. 106, p. 365, 1973.
          .and peaking time varies as their is no standard method for defining RC time constants in semi-Gaussian shaping networks.


"Care should he^taken to ensure that the "Co saiurc:
Roney, W., and W. Seale, "Gamma-Ray Intensity Standards Knoll, G. F., Radiation Detection and Measurement, for Calibrating Ge(Li) Detectors for the Energy Range 200
                  6 IEEE Sid 325-197 1, op. cit., Section 3.                          encapsulation    is *.thin cenough. (<1 0( ng/cut 2 plsi ic or . tte equivalent) so that self absorption in the source itself is nor
John Wiley and Sons, New York, 1979.
                  7Ibid., Section 5.2.                                                significant.


__    _"                                     "    '."                          5.9-3
1700 keV," Nuclear Instruments and Methods, Vol. 171, p. 389, 1980.


witlh less than a IT0 relathe increac in the FWHM and                  well-known pillma ray soutces and the proecdure
This book provides extensive discussion of all types of radiation detection systems, including high-resolution Sher, R., and S. Untermeyer, The Detection of Fissionable gamma ray spectroscopy systems. In particular, Sec Materials by Nondestructive Means, American Nuclear tion D deals exclusively with solid state detectors, and Society Monograph, 1980.
          . W.M  *      ol'the 1 2 keV peak as" iCOipared to th6 values        dscribed in the literature.'
      *.. obtained at          1.O
                                  c.                  .
                                                                                      The long.term stability requirement for the system's
          4. Peak-to-Coinpton Ratio.                                            zero channel and gaiti shOuld be defined as follows: the drift in die position of a spectrum peak front a s L(S The peak-lo-Comlpton. ratio for tie selI1,i)                                                  calibration source shotld be less thin 0.1"'l (compared to
          .. .33MeV peak Irom a            Co source. as detined in I-EE        full. scale) in a 24-hour period at constant room Standard 325-197 1' should be greater than the values                teln'perature. (For example, tie centroid of a calibration peak placed in approximately channel 4000 of specilied in. T'lhk&#xfd; 2 for 'corresponding detector                                                                            a 4096
    -e fficienc-ies.                                                            channel spectrum should not vary in position by more than .4 channels over a 24-hnur period.) Tiie temperature
    *    (System 1Il) Tlifis specification is not applicable.                  coefficient of the systenm's zero channel and gain should
                                                                                                      0
                                                                                be less thau 0.02%  .,,C  in the temperature range from O"
                                                                                to 50"C.


*        5. Linearity and Stability
Section F is devoted to detector electronics and pulse processing.                                                     This relatively short book summarizes the principles of most nondestructive assay methods and briefly describes Kuil, L A., "An Introduction to Ge(Li) and NaI Gamma many typical applications, including those of high Ray Detectors for Safeguards Applications," Argonne resolution gamma ray spectroscopy. Chapters 3 and 5 National Laboratory, ANL-AECA-103, 1974.
                                                                                      " R. C. Greenwood, R. G. Ilcimer. and R. G. Gehrke.


(Systenis I, Ii, Ill) The integral non linearity of the      "Precise Comparison and Measuiement of Gamma-Ray Energies data acquisition system's ener,, calibration should be                with a GOtLi) Detector I. 50-420 kcV,," Nuct. Instr. and Methods less than 0.2-." over the top 95%' of the ADC. range. The            77. 141 (197W).
are of particular interest since they deal, respectively, with nuclear detection methods and passive NDA
  *          ystcm n.nlitiarity should be measured uwing a set of                        R. G. Wnlmer, R. C. Greenwood and R. G. Gehrke,
P. W. Nicholson, Nuclear Electronics,John Wiley and Sons, techniques. The book also contains many references to New York, 1974.
                                                                                  "Precise Comparison and Measurcment of Gamma-Ray Energies with a Ge(Li) Detector It. 400-1300 ke,," Nuclear. Insir. and
            'I* -:l "Sid 325-1971 , p. cit.. Section 3.4.                        Methods 96. 173 (1971.)
                                                                            5.9-4 m


APPENDIX A
original papers and reports.
                      COMPONENT SPECIFICATIONS                               


===3. Preamplifiers===
5.9-6
          1. Detector Crystal Geometry                                              S(Systems 1, II) It            tamy cases        prcampliler.s Comp'it iible with nuclear material                    speclroscorpy (Systcms. I,.II)The dctector should be of' tie closed applications are purchased in combination              with :aGe( Li)
        end.. coaxial drift. right :circular. cylinder t)yp: 0hi crystal as a package. The detector                    specifications con figuraation has the Iit;ixinttitn fraction oftusable activc t here fore      relate    to  the    d e t Cc Itor-prCetupliflCr volume:fit r detecturslof noderate tolhigh cfliciency. The combi;ia lion: however. tile following additiUnal crystal diameter should be approximnailclv equal to ib specifications should he included in the selection of .ill length to minimizc any Unusual e'f'icienicy vs. gcunteirv            optimal system. A charge sensitive preamtplihlie shtmild
    *    effects. The active volume or the detector should                      he nmottned on t lie cryostat near lite detector. The field comprise at least '0'i.- 61' t[lie total crystal volumne with        effect transistor (WET) in ite first staye o1 tlie the undrifled core diameter kept as sitall as                          preanipli*',      Ti..mld lw operated at room tellrirature economically possible. This maximizes [lie prob:tabilily!            (_300"i'K      ' Tile detector sihtuld he d.c. coripled (:Is that a ganima-ray- interactiui will appear ill tile fill]
                                                                              opposcd .o c.,p:,.'itively coupled) to tile aic of tle itpul energy pcak of the spectrum. (Note: The specification *              stage of' tire 1i c.1triplilher for better ctenergy resohulion.


ott peak-to-Compton ratio given in Section ('.4 is directly related to the crystal's aclive/total volume atio.]                The tti lowing procedures arc iccniittended to minimize the probability of destroying thei F1 " dtie to (System Ill) The detector shotuld be of the planar                detector warmup or high-voltage Irantsients. Posilivc high type. Small detectors of this configuration offer the best            voltage should be used, and the: e should be at lcast one resolution available for low-energy, gamma rays.                      filter section placed in t(le higl*-voltage system interntal Operating specifications are given in Section C.2 that                to the cryostat. At least one filter should also be placed define the allowable thickness of detector surface .dead              external to the cryostat to reduce tile possibility of shorl layers" which absorb low-energy gamma rays before                      circuiting due to condensate formation on thie internal they interact in the detector's active volume.                        filter. The total RC time constant of the filter network S        (Systems I,      II, Ill) Methods for specifying the physical size for tlte: detector crystals are covered in should be at least 30 seconds.
VALUE/IMPACT STATEMENT
                                                                          1.3.4 Public


(System I1l) Sanme as above for Systenms I and II
===1. PROPOSED ACTION===
        Section C.2.                                                          except that the FET in the preantiplifier's first stage should he located within the cyrostat and operated it
                                                                          No adverse impact on the public can be foreseen.
      *  2. Detector Mounting and Cryostat Description                          liquid nitrogen (LN) temperature. Att LN cooled 17ET is required, to achieve the excellent eiergy resolution (Systems 1, III)      There are four detector cryostat          characteristics of this system.


configurations Which are typically' available: (I) right angle dip-stick, (2) upright dip.stick. (3) gravity feed.            4. Main Amplifier and (4) side entry (portable). Of these, the right angle dip-stick is widely used for Systems I and I1 and the                        (Systems I, I1. i11) A main amplifier with adjustable upright dip-stick for System III: the configuration                    pgin should include unipolat. senti-Gaussia," pulse selected should be that considered to be most useful for              shaping networks with adjustable titiCe constants a specific application. For reliable operation. the vacuum            corresponding to peaking times between I atnd S usec. ( I
1.1 Description
        in the detector housing should be maintained by a                      to 4 psec peaking times are typically used for Systemts I
                                                                      1.4 Decision on Proposed Action
        zeolite getter. It is recommended that the liquid nitrogen            and II while peaking titnes as long as 8 ,isec could be Dewar have a minimum capacity of about 30 liters and a                used in System I1l.) This choice fl" antplifier provides holding time of at least 10 days. The Dewar should have                minimum resolving time for a given energy resolution a connection which allows replenishment of the liquid                  and sufficient flexibility to optimize the amplifier nitrogen supply without removing the cryostat. A                      characteristics for most' counting conditions. Nominal separate high-voltage input to the cryostat housing                    specifications to aid in identifyiing this class of should be provided in the event it is necessary or                    amplifiers. commonly referred to as spectroscopy desirable :to apply a detector bias which exceeds the                 amplifiers, include the following: linear range 0 to IOV.
-"     Licensees authorized to possess at any one time more than one effective kilogram of special nuclear material The guide should be revised to reflect improvements in (SNM) are required in &sect; 70.51 of 10 CFR Part 70 to techniques, to bring the guide into conformity with current establish and maintain a system of control and account practice, and to provide a list of pertinent information ability so that the standard error of any inventory difference      currently available.


rating of. the preamplifier's high-voltage input. It is                integral nonlinearity          <0.05%. temperature stability recommended that the high-voltage input be clearly                    <100 ppm gain shiftrc. attd thermal noise <5.,V rats marked and located at least 2.0 cm from the S  preamplifier signal output. The distance between the detector's front surface. and the window in the housing should be less than or equal to 1.0 cm to allow one to
ascertained as a result of a measured material balance meets established minimum standards. The selection and proper           
                                                                                    2 ISystern II only) Tle preamplifncr\ First stape F-lV may be located within the keryo,;iai and operated at liquiid nitmtgen temnperatures, but in order to faeiliLaie poSible ITT
        achieve minimal detector-sample separations when                      replacement.    it is recomntended  Ihat  a detectorlhe    electu-d I..    necessary.                                                            which attains adequate energy resolturion with an unct'i*thd l.T.


5.9.5 L~.
===2. TECHNICAL APPROACH===
  application of an adequate measurement method for each of the material forms in the fuel cycle are essential for the          Not applicable.


referred t0 the input for 4 u.sec peaking times (the.noise level varies inversely withthc peaking time). The main a stable pulsershould not shift by more than one channel over a 24,hour period.for a line voltage of 115V
maintenance of these standards.
                                                                                                                                        0.,:..
  anipliier %shouldbe a standard NIM' 3 module.                            - li,. 50-65 Hz,7and at constant room temperature.


(Note: The. ADC. drift and.linearit
Many types of nondestructive assay (NDA) measurements         


====y. specifications are====
===3. PROCEDURAL APPROACH===
            .. .......tin atesgreater than. 0-1 cps, problems At                                                            closely ..re!'ttcd :to the.. overall system stability and U."I a'dtgtadation es          of the:energy resolution resulting in lirearity operating specifications described in Section
  on SNM can involve, or even require, a high-resolution gamma ray spectroscopy system. The proposed action is to               Of the alternative procedures considered, revision of the provide some general guidelines in the selection of such existing regulatory guide was selected as the most advan systems and to point out useful resources for more detailed         tageous and cost effective.
    . loss of counts. in the. spectrurn peaks begin to occur.            C.5.)
"..Thes effects are due. to.the overlap of portions of tw'o or
  0.orL pulses in.time and to bas.line fluctuations. The                        "Fhc ADC should be capable of being DC coupled to
  .t .
  nagniitude      of. Ihese effects can be mininized by tlie            the main aniplifier in order that BLR circuits can be inclision Ofatile. following Ifatures in the amplifier's                used. A digital: offset capability in the ADC is desitl-. (I ) a. b.baseline.. restorer.:(BLR) circuit at. the           recommended. (Note: In some systems the ADC is an amnphi        ocvrvut.pu and. (21) pole-zero. cancelled coupling         integral -part of a multichannel analyzer, a unit which networks.7TheiBLR circuit shouldbe adjustable for both                also performnsi.the, funct ions .of.data storage, display, and low ind high couhiting lte..conditions..            .                sometimes rudimentary analysis. These latter functions are taken. up :in Part 2 of this serie


====s. In multichannel====
information on their assembly, optimization, and use in material protection measurements.
  5. Analog to Digital Converter (ADC)                                  analyzersystems, however, the ADC function is usually specified separately and can be compared with the above (Systems I, Ii,.ll) The ADC should be capable of                recommendations.)
  digitizing pulse amplitudes from the amplifier in the range of 0 to 10 volts in at least 409)6 channels. The                      (System 1) For certain applicatiuns where energy frquency of thle internal clock should be at least 50                  resolution is definitely not critical, all the ADC
  ne,,ah,'tz to handle high counting rates with nominal                  specifications above are applicable with the exception
" AD)C dead time losses. The integral nonlinearity should                  that a 1024 channel capacity with a 1024 digital offset be less .than 0.15% over the top 95%, of full scale and the            may be adequate to provide a sufficiently small energy differential nonlinearity should be less.than 1.0% over                interval per channel (keV/channel) to cover a limited the. top 95% of full scale for semi-Gaussian pulses with              energy range of.. interest. It should be emphasized, peakingtirnes of I.to psec. These linearity specifications            however, that this choice may restrict the effective use are. not . siringent. but:. are *adequate to enable                    of the system for other applications.


identification of unknown peaks. which may.. appear in a spectrum...                                                              6. Power Supplies The short-term zero channel arid gain drifts should                    (Systems I,. II, .111) The system power supplies
4. STATUTORY CONSIDERATIONS
* be < .01%/f(?C and 4 .02%0rC, respectively (the                          (detector high- voltage, preamplifier, and NIM bin)
    1.2 Need for Proposed Action                                        4.1 NRC Authority Regulatory Guide 5.9, which provides guidance in this Authority for the proposed action is derived from the area, has not been updated since 1974 and does not contain Atomic Energy Act of 1954, as amended, and the Energy a list of pertinent information currently available in the Reorganization Act of 1974, as amended, and implemented literature.
  percentage refers to full scale), in the temperature range              should be capable of operating the system within the front 00. to 500C. For long term stability, the peak from                operating specifications listed in Section C.i when supplied with 115 volts (+/- 10%) at 50 to 65 hertz (at
        *3 NtM-Nuclear Instrument Module. see USAEC -Technical            constant room temperature). The detector bias power Information Document. Standard Nuclear Instrument Modules.              supply should have an adjustable output that is short Revision 3. TID-20893 (1969L.                                            circit protected.with automatic power restoration after
        .t'4For more details on BLR circuits see V. Radeka, "Effect      removal of the short. The maximum outputvoltage .is of 'Baseline Restoration' on Signal-to-Notre Ratio in Pulse              determined by detector requirements; 5 kilovolts is Amplitude Mteasurements," Rev. Sci. Instr. 38. 1397 ( 1967).            sufficient for most applications.


5.9-6
through the Commission's regulations.
 
1.3 Value/Impact of Proposed Action                                4.2 Need for NEPA Assessment
        1.3.1 NRC Operations The proposed action is not a major action that may significantly affect the quality of the human environment The experience and improvements in detector technology and does not require an environmental impact statement.
 
that have occurred since the guide was issued will be made available for the regulatory proces


TABLE 1 ENERGY RESOLUTION AND PEAK SHAPESPECIFICATIONS
====s. Using these updated====
                                              SYSTEM I
                                                                        5. RELATIONSHIP TO OTHER EXISTING OR
Calibration Source Gamma Ray Energy                              FWHM (keVI                              FW.02MtFWHM
    techniques should have no adverse impact.                               PROPOSED REGULATIONS OR POLICIES
                                                1.6                                  less than 2.7
        1.3.2 Other Government Agencies                                    The proposed action is one of a series of revisions of existing regulatory guides on nondestructive assay tech Not applicable.                                                 niques.
'ic o- 133Q key                                25                                    less than 2.8 SYSTEM II
&#xfd;"Co- 122 keV                                    1.0                                  less than 2..
  0
6'  CO- 1332 key                                1.9                                  less titan 2.8 SYSTEM III
  'Co-5.9 keV (Fe X-ray)                        0.32                                less than 2.5 S'7Co- 122 keV                                    0.55                                less than 2.5 TABLE 2.


PEAK-TO-COMPTON RATIO VS. DETECTOR EFFICIENCY Miiu Detector Efficiency                                  Minimum (As defined in Section C.2)                        Peak-to-Compton Ratio
1.3.3 Industry                                                  6. SUMMARY AND CONCLUSIONS
                          5%                                            20:1
        Since industry is already applying the more recent Regulatory Guide 5.9 should be revised to bring it up to detector technology discussed in the guide, updating these          date.
                        1070                                            3o:1
                        1o%                                              35:1
                        20%                                              38:1
                                                  59.7


LIQUID
techniques should have no adverse impact.
NITROGEN
'DEWAR
                                                                  DIGITAL OUTPUT
                                                    ANALOG        TO DATA STORAGE
        PREAMPLIFIER          AMPLIFIER          TO DIGITAL      DISPLAYS, DATA
                                                  CONVERTER        REDUCTION AND
                                                                  ANALYTICAL MODULES
        Figure 1.-BLOCK DIAGRAM OF A Ge(Li) DATA ACQUISITION SYSTEM
                                  5.9-8


..,UNITED STATES
5.9-7
                          ATOMIC =ENERGY COMMISSION
                                WASHINGTON.  C._ 20545 June 29,    1973 TO REGULATORY GUIDE DISTRIBUTION LIST (DIVISION 5)
  Enclosed for your information and use are copies (which may be reproduced)
  of the following regulatory guides:
      Regulatory Guide 5.7 - "Control of Personnel Access to Protected Areas, Vital Areas, and Material Access Areas"
      Regulatory Guide 5.8  - "Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations."
      Regulatory Guide 5.9 - "Specifications for Ge(Li) Spectroscopy Systems for Material Protection Measurements - Part I:
                              Data Acquisition."
  The Division 5 Regulatory Guides are being developed to provide guidance on the acceptability of specific materials and plant protection related features of nuclear facilities licensed to possess special nuclear
* umaterial.  Enclosed are a table of contents of issued Division 5 guides and a list  of additional guides in this division currently being developed.


Sincerely, es~erog~e~rst Director of Regulatory Standards Enclosures:
UNITED STATES
  As stated}}
NUCLEAR REGULATORY COMMISSION      emPST CLASS MAIL
                                  POSTAGE FEEISPAID
    WASHINGTON, D.C. 20585              USNRC
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                                    PERMIT MeoSL
        OFFICIAL BUSINESS
    PENALTY FOR PRIVATE USE, $300
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Revision 2*

December 1983 U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 5.9 (Task SG 042-2)

GUIDELINES FOR GERMANIUM SPECTROSCOPY SYSTEMS

FOR MEASUREMENT OF SPECIAL NUCLEAR MATERIAL

to boxes and cans of uncharacterized waste materia

l. Meas

A. INTRODUCTION

urement conditions also vary widely from controlled laboratory environments to the unpredictable plant environ Section 70.51, "Material Balance, Inventory, and Records ment that can be hostile to the measurement equipment Requirements," of 10 CFR Part 70, "Domestic Licensing and can often contribute serious background interferences of Special Nuclear Material," requires, in part, that licensees to the spectral data. As a result, there is no single gamma authorized to possess at any one time more than one ray assay system that can be effective in all cases. The effective kilogram of special nuclear material establish and system chosen for a particular NDA task must therefore be maintain a system of control and accountability so that determined from careful consideration of all factors that the standard error (estimator) of any inventory difference, may affect the measurement and of the requirements for ascertained as a result of a measured material balance, the precision and accuracy of the assay.

meets established minimum standards. The selection and proper application of an adequate measurement method for The scope of this guide is limited to the consideration of each of the material forms in the fuel cycle is essential for high-resolution gamma ray spectroscopy with lithium-drifted the maintenance of these standards. germanium, Ge(Li), or high-purity germanium, HPGe (also referred to as intrinsic germanium, IG), detectors. No Many types of nondestructive assay (NDA) measurements discussion of thallium-activated sodium iodide, NaI(Tl), or on special nuclear material (SNM) can involve, or even lithium-drifted silicon, Si(Li), gamma ray systems is

> require, a high-resolution gamma ray spectroscopy system. presented. In addition, no discussion of specific NDA

This guide is intended both to provide some general guide applications of gamma ray spectroscopy is provided. The lines acceptable to the NRC staff for the selection of such measurement procedures (including calibration), analysis systems and to point out useful resources for more detailed methods, Inherent limitations, and overall precision and information on their assembly, optimization, and use in accuracy attainable are specific to each application and are material protection measurements. therefore the subject of separate application guides. Guide lines for measurement control, calibration, and error Any guidance in this document related to information analysis of NDA measurements are dealt with in detail in collection activities has been cleared under OMB Clearance Regulatory Guide 5.53, "Qualification, Calibration, and No. 3150-0009. Error Estimation Methods for Nondestructive Assay,"

which endorses ANSI N15.20-1975, "Guide to Calibrating

1

B. DISCUSSION

Nondestructive Assay Systems." ANSI N15.20-1975 was reaffirmed in 1980.

1. BACKGROUND

ýX of the major commercial vendors of Ge(Li) and Gamma ray spectroscopy systems are used for NDA of HPGe detectors and the associated electronics maintain various special nuclear material forms encountered in the up-to-date documentation on the specifications of currently nuclear fuel cycle, both for quantitative determination available equipment, as well as a variety of useful and infor of the SNM content and for the determination of radio mative notes on applications. This literature is available nuclide abundances. The substantial number of channes in this revision has made it Impractical to Indicate the changes with lines in the margin.

the American Applications of high-resolution gamma ray spectroscopy Covpies of this standard may be obtained fromNew

1 Standards Institute, Inc., 1430 Broadway, York, New have multiplied greatly in recent years. The samples encoun National York 10018.

tered range from fresh fuel rods and reprocessing solutions Comments should be sentCommissionto the Secretary of the Commission.

USNRC REGULATORY GUIDES U.S. Nuclear Regulatory Washington, D.C. 20555.

make available to the Attention: Docketing and Service Brancn.

Regulatory Guides are Issued to describe andstaff of implementing public methods acceptable to the NRC to delineate tech- The guides are Issued In the following ten broad divisions:

specific parts of the Commission's regulations, niques used by the staff in evaluating specific problems or postu 1. Power Reactors 6. Products Regulatory iated accidents or to provide guidance to applicants. with 2. Research and Test Reactors 7. Transportation Guides are nof substitutes for regulations, and compliance from those set 3. Fuels and Materials Facilities S. Occupational Health them Is not required. Methods and solutions different 9. Antitrust and Financial Review

4. Environmental and Siting out in the guides will be acceptable If they provide of a permit the a basis for or 5. Materials and Plant Protection 10. General findings requisite to the issuance or continuance license by the Commission. Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe This guide was Issued after consideration of comments received from Government Printing Office.

in these cific divisions is available through the the public. Comments and suggestions for Improvements will be revised, as Information on the subscription service and current GPO prices may guides are encouraged at all times, and guides be obtained by writing the U.S. Nuclear RegulatorySales Commission, appropriate, to accommodate comments and to reflect new informa- Washington, D.C. 20555, Attention: Publications Manager.

tion or experience.

from the manufacturers upon request, and the potential an integral part of the detector package. The preamplifier customer may use this literature as a source of the most signal is further amplified and shaped and is then converted current information on the highest quality systems available.

into digital information that can be stored, displayed, and otherwise processed by the data reduction and analytical Finally, the potential user ought to consult with those components of the system.

individuals currently active in the field of nondestructive assay of special nuclear material and seek their advice in the

4. TYPES OF SYSTEMS

particular assay problem being considered.

High-resolution gamma ray spectroscopy systems are

2. BIBLIOGRAPHIC INFORMATION distinguished primarily by the type (p-type or n-type) and the configuration (planar or coaxial) of detector used. For An annotated bibliography is included in this regulatory assay applications involving the measurement of low-energy guide to provide more detailed information on spectros gamma radiation (i.e., energies below approximately copy systems and their use. 200 keV), a thin planar HPGe or Ge(Li) crystal is most appropriate. A coaxial detector crystal with a larger volume Elementary introductions to the concepts associated is much better suited for higher energy gamma ray measure with the application of high-resolution gamma ray spectros ments (i.e., for energies above approximately 120 keV).

copy to problems of nuclear material assay are available in The distinction between these two types of detectors is not Augustson and Reilly and in Kull. These works discuss sharp. For instance, there maý be some applications above the physical processes of gamma ray detection and impor 120 keV in which a planar detector would be useful to tant instrumentation characteristics. More advanced dis render the system less sensitive to interferences from cussion of gamma ray detectors and associated electronics ambient high-energy gamma radiation.

may be found in Knoll and in Adams and Dams. A thorough treatise on the associated electronics is available in Nicholson.

It should be noted that Ge(Li) detectors have no real In addition, extensive discussion of a variety of NDA tech advantage over HPGe detectors with comparable perform niques and the implementation of some of these techniques ance specifications. In addition, Ge(Li) detectors require with high-resolution gamma ray spectroscopy may be constant liquid nitrogen (LN) cooling, even when not in found in Sher and Untermeyer, in Rogers, and in Reilly and operation. HPGe detectors are, of course, also operated at Parker. Detailed descriptions of detector efficiency and LN temperature, but they can be stored at room tempera energy calibration procedures are available in section D of ture. This is an advantage to potential users who may have Knoll and also in Hajnal and Klusek; in Hansen, McGeorge, extended plant shutdowns. It also prevents complete loss and Fink; in Hansen et aL; and in Roney and Seale. of a detector due to operator procedure error, which can happen with a Ge(Li) detector when Ll4 cooling is not Relevant technical information beyond the introductory level, including nomenclature and definitions, is contained continuously maintained. This added convenience and the greater ruggedness of the HPGe detectors make them K

in three useful standards of the Institute of Electrical and especially attractive for in-plant NDA applications.

Electronics Engineers, ANSI/IEEE Std 301-1976, "Test Procedures for Amplifiers and Preamplifiers for Semi 5. EQUIPMENT ACCEPTANCE PRACTICES

conductor Radiation Detectors for Ionizing Radiation," 2 ANSI/IEEE Std 325-1971, "Test Procedures for Germanium Equipment descriptions and instructional material Gamma-Ray Detectors" 2 (reaffirmed in 1977), and ANSI/

covering operation, maintenance, and: servicing of all IEEE Std 645-1977, "Test Procedures for Hifh-Purity electronic components are supplied by the manufacturer Germanium Detectors for Ionizing Radiation,"" which for all individual modules or complete systems. Such supplements ANSI/IEEE Std 325-1971. These describe descriptions should include complete and accurate sche detailed techniques for defining and obtaining meaningful matic diagrams for possible in-house equipment servicing.

performance data for Ge(Li) and HPGe detectors and Complete operational tests of system performance are to be amplifiers. made at the vendor's facility, and the original data are

/

supplied to the user upon delivery of the equipment.

3. FUNCTIONAL DESCRIPTION Extensive performance testing of all systems by the user is generally not necessary. 3 However, qualitative verification A block diagram of a typical high-resolution gamma ray of selected equipment performance specifications and spectroscopy system is shown in Figure 1. In such a system, detector resolution is recommended.

the solid state Ge(Li) or HPGe detector converts some or all of the incident gamma ray energy into a proportional It is necessary to have calibration sources on hand to amount of electric charge, which can be analyzed by the verify the operational capabilities of the system. The subsequent electronics. The detector output is converted following radioactive sources (with appropriate activities)

into an analog voltage signal by the preamplifier, which is

3 Although the quality control and presh.pment testing may be obtained from the Institute of Electrical and dures of the commercial vendors of detectors and associatedproce.elec.

Electronics Engineers, Inc., 34S East 47th Street, New York, New onuic, h~ave improved and are quite dependable, some user verifica.

York 10017. tion of the specifications claimed by the manufacturer Is strongly recommended.

5.9-2

I I

I \ I

I I

I Uquld I

Nitrogen High Dewa Voltage I (Cooling) Supply Spectrum f .Stabilization I

Spectroscopy I Analog-to-Digital I Detector Preamplifier Amplifier Conversion II

I

I. I , I

II

Count I

Rate Scaler Data storage, display, and data reduction and analysis I

components I

I I

FIGURE 1 A block diagram of a typical setup of a high-resolution gamma ray spectroscopy system. The dashed boxes indicate which sets of modules are usually packaged as one component in commercially available systems. Liquid nitrogen cooling of the detector is required for proper operation of the system, but the field-effect transistor (FET) in the preamplifier input stage may or may not be cooled, depending upon the type of detector used and the energy resolution desired. A scaler is shown connected to the main amplifier, a common method of monitoring the total system count rate. For long-term data acquisi tion, spectrum stabilization is recommended, and the method is indicated here by a stabilizer module in communication with the analog-to-digital converter (ADC).

5.9-3

will provide sufficient counting rates to verify the energy will always have LN-cooled FET preamplifiers in order to resolution specifications of the manufacturer and to carry achieve the excellent resolution of these systems. The out any other performance tests desired by the user: preamplifier feedback loop may be either pulsed optical or resistive, 7 and the system will have fairly modest rate

60Co 10-30 pCi, Gamma ray energies: 1173,1332 keV

57 capabilities in the range of 5000 MeV/sec. 6 It is important CO 1-10 j0i, Gamma ray energies: 14, 122, 136 keV

to decouple the detector from noisy mechanical environ ments to avoid microphonic pickup.

C. REGULATORY POSITION

2. ELECTRONICS PERFORMANCE

Ge(Li) or HPGe gamma ray spectroscopy data acquisi tion systems meeting the general guidelines outlined briefly For ease of use, maintenance, and replacement of the below are considered more than adequate for use in SNM components in a high-resolution gamma ray spectroscopy assay requiring resolution better than that obtainable with system, the electronic components should be standard Na! detectors. The potential user should select the detector nuclear instrument modules (NIM) (Ref. 1), with the and associated electronics that meet the needs of the partic possible exception of the pulse-height analysis (Le., multi ular assay task required, with careful consideration of all channel analyzer) components. Pulse signals should be factors that could affect the quality of the assay. transmitted from module to module in shielded coaxial cable to minimize the effects of possible electronic noise

1. DETECTOR PERFORMANCE from nearby machinery at the measurement site. The cables should have a characteristic impedance that matches the Excellent performance, routinely available in coaxial terminations used in the NIM modules (generally 93 ohms).

germanium detectors, may be represented by energy resolutions (FWHM) 4 of approximately 1.7 keV at 1332 keV The system power supplies (detector high voltage,

( 60 Co) and approximately 0.7 keV at 122 keV ( 5 Co) for preamplifier, and NIM bin) should be capable of operating detectors with efficiencies up to 20 percent. 5 The full width the system within the operating specifications when supplied at 0.1 maximum (FWTM) for such detectors is typically up with 115 volts (+10 percent) at 50 to 65 hertz (at constant to 1.9 times the FWHM. For these higher efficiency detec room temperature). The power supplied for the detection tors, "peak-to-Compton ratios" are usually quoted in the system should be stabilized against voltage shifts in order to range of 25 to 40. These ratios are strong functions of maintain resolution. The output voltage of the detector bias resolution, efficiency, and exact detector crystal geometry, supply is determined by the detector requirements; 5 kilo and no typical values can be given without knowledge of all volts is sufficient for most applications.

of these parameters. Coaxial detectors with this kind of resolution will usually have cooled field-effect transistor The main amplifier, commonly referred to as the spectros (FET) preamplifiers and an energy-rate capability of copy amplifier, should have variable gain and pulse-shaping approximately 50,000 MeV/sec. 6 Room temperature pre controls for maximum setup flexibility. Most high-quality amplifiers have somewhat worse resolution but have rate amplifiers are equipped with baseline restoration and capabilities on the order of 150,000 MeV/sec. pole-zero cancellation circuits (Ref. 2), which greatly improve the resolution that can be achieved on a routine The resolution of planar detectors is a stronger function basis. Baseline restoration is essential for assay situations in of the crystal size and shape than that of coaxial detectors, which count rates in excess of several kilohertz are antici so representative resolutions cannot be given over a range of pated. Pulse pileup suppression is also a useful feature, if sizes. As an example from the middle of the range of sizes available; it may be found in some spectroscopy amplifiers usually offered, an excellent 2 cm 3 planar detector (le., and even in separate NIM modules designed for that purpose.

2 cm 2 front face area x 1 cm thick) would have a resolution of approximately 0.5 keV at 122 keV (5 7 Co) and 0.21 keV Electronic components should be obtained with state-of at 5.9 keV (Mn X-ray from SaFe decay). Planar detectors the-art linearity and temperature sensitivit

y. Maintenance

4 The full width of the gamma ray photopeak at half of its of long-term gain stability may require the use of a spec maximum height (FWHM) is defined in ANSI/IEEE Std 301-1976. trum stabilizer. Centroid variations of a stabilization peak SThe full-energy peak efficiency (in percent) is defined relative of less than one channel in a 4096-channel spectrum are to the full-energy peak efficiency of a 3-in. J.n. NaI(TI) scintilla achievable with commercially available stabilizer modules.

tion detector for 1332-keV gamma rays v Co) at a source-to. Stabilization peaks can be provided either by a pulser or by detector distance of 25 cm. The detailed procedures for determining the efficiency in accordance with this definition are presented in a radioactive source. Generally, a radioactive source is Section 5.2 of ANSI/IEEE Std 301-1976.

preferred because it contributes less distortion to the

6 Counting rate capabilities, expressed In MSV/sec, denote the gamma ray spectrum and has a stable (although decaying)

maximum charge-to-voltay. conversion rate of which the pre emission rate. Furthermore, stabilization peaks from amplifier Is capable. For " Co, a SO,000-MeV/sec rate capability corresponds to a pulse iunting rate limitation of approximately natural sources may be obtained from existing peaks

80,000 counts/sec. For Co a 000-MeV/sec rate capability also in the assay spectrum itself, which simplifies the assay corresponds to a pulse rate limitation of approximately 80,000

counts/sec. Of course, nuclear material assays should be performed at count rates well below these limiting values in order to minimize 7 Feedback methods for charge-sensithve preamplifiers are dis rate-related losses from pulse pileup and dead time. cussed thoroughly in Chapter 5 of Reference 2.

K\

5.9-4

on the sensitivity, precision, and accuracy of any assay. The setup. Dead-time and pileup corrections may also be range of gamma ray energies of interest also determines the performed using a pulser or a separate radioactive source type of gamma ray detector appropriate for optimum fixed to the detector. The latter method is preferred for the efficiency.

reasons stated above.

b. Full-Energy Peak Area Determination: The proce

3. SYSTEM SELECTION AND USE dure for extracting this fundamental information from the spectral data will be determined by the complexity of the The detailed requirements and constraints of a particular gamma ray spectra as well as the intensity and complexity measurement situation will cause wide variation in the of the gamma ray background at energies near the peaks of optimum choice of systems, even within a fairly well-defined interest.

application. For example, a requirement for high through put may dictate higher efficiency detectors and highly c. Gamma Ray Attenuation by the Samples and Sur automated data acquisition electronics. Anticipated inter rounding Materials: Corrections for this effect are essential ferences from uranium, thorium, or fission products may for accurate assays. The importance of this correction will make the best possible system resolution the most impor increase as the gamma ray energies of interest decrease and tant consideration. Severe operating environments may the absorptive power of the sample and surrounding mate make the use of digital stabilization highly desirable. Con rials increases.

straints of space and location could dictate an unusually small LN dewar with automatic filling capacity. The list of such considerations in a given situation can be long, and All of this emphasizes that by far the most important each situation should be considered carefully and indi factor in choosing an appropriate data acquisition system, vidually in order to achieve a system that can acquire the in Implementing proper assay procedures, and in supervising required measurement data. the assay operations is a highly competent person, prefera bly experienced in gamma ray spectroscopy and its appli Beyond the choice of data acquisition systems, many cation to assay measurements of special nuclear materials.

other factors influence the successful use of gamma ray Such a person, with the assistance of the existing literature spectroscopy in quantitative assay measurements. Some of and of others in the gamma ray field, will be able to consid these are: er a particular application in detail and choose an appro priate detector and electronics to create a data acquisition a. Gamma Ray Signatures: The energies and intensities system that is well suited to the required assay task.

of the relevant gamma rays place fundamental restrictions

5.9-5

REFERENCES

1. L Costrell, "Standard Nuclear Instrument Modules,"

2. P. W. Nicholson, Nuclear Electronics, John Wiley and U.S. Atomic Energy Commission, TID.20893, Revi Sons, New York, 1974.

sion 3, 1969.

BIBLIOGRAPHY

Adams, F., and R. Dams, Applied Gamma-Ray Spectros This is an extensive treatise on electronics systems copy, Pergamon Press, New York, 1970.

associated with high-resolution detectors. Detailed descriptions are given of detector preamplifiers, pulse This work provides a comprehensive coverage of back shaping, rate-related losses, pulse-height analysis, and ground material pertinent to the gamma ray spectros spectral resolution.

copist. Considerable information is provided on both Nal and Ge detectors. Reilly, T. D., and J. L Parker, "Guide to Gamma-Ray Assay for Nuclear Material Accountability," Los Alamos Augustson, R. H., and T. D. Reilly, "Fundamentals of Scientific Laboratory, LA-5794-M, 1975.

Passive Nondestructive Assay of Fissionable Material," Los Alamos Scientific Laboratory, LA-565 I-M, 1974.

This report briefly covers the principles involved in using gamma ray spectroscopy in the quantitative assay of This manual contains helpful introductory descriptions SNM and attempts to describe both capabilities and of NDA applications of gamma ray spectroscopy, as well limitations of gamma ray assay techniques. The report as some discussion of gamma ray detection systems.

also includes a description of procedures for determining Hajnal, F., and C. Klusek, "Semi-Empirical Efficiency plutonium isotopic ratios.

Equations for Ge(Li) Detectors," Nuclear Instruments and Methods, Vol. 122, p. 559, 1974.

Rogers, D. R., "Handbook of Nuclear Safeguards Measure ment Methods," Nuclear Regulatory Commission, NUREG/

Hansen, J., J. McGeorge, and R. Fink, "Efficiency Calibra CR-2078, 1983.

tion of Semiconductor Detectors in the X-Ray Region,"

Nuclear Instruments and Methods, Vol. 112, p. 239, 1973.

Chapter 5, "Passive Nondestructive Assay Methods,"

Hansen, J., et al., "Accurate Efficiency Calibration and contains descriptions of many applications of high K

resolution gamma ray spectroscopy, as well as many Properties of Semiconductor Detectors for Low-Energy references to original papers and reports.

Photons," Nuclear Instruments and Methods, Vol. 106, p. 365, 1973.

Roney, W., and W. Seale, "Gamma-Ray Intensity Standards Knoll, G. F., Radiation Detection and Measurement, for Calibrating Ge(Li) Detectors for the Energy Range 200

John Wiley and Sons, New York, 1979.

1700 keV," Nuclear Instruments and Methods, Vol. 171, p. 389, 1980.

This book provides extensive discussion of all types of radiation detection systems, including high-resolution Sher, R., and S. Untermeyer, The Detection of Fissionable gamma ray spectroscopy systems. In particular, Sec Materials by Nondestructive Means, American Nuclear tion D deals exclusively with solid state detectors, and Society Monograph, 1980.

Section F is devoted to detector electronics and pulse processing. This relatively short book summarizes the principles of most nondestructive assay methods and briefly describes Kuil, L A., "An Introduction to Ge(Li) and NaI Gamma many typical applications, including those of high Ray Detectors for Safeguards Applications," Argonne resolution gamma ray spectroscopy. Chapters 3 and 5 National Laboratory, ANL-AECA-103, 1974.

are of particular interest since they deal, respectively, with nuclear detection methods and passive NDA

P. W. Nicholson, Nuclear Electronics,John Wiley and Sons, techniques. The book also contains many references to New York, 1974.

original papers and reports.

5.9-6

VALUE/IMPACT STATEMENT

1.3.4 Public

1. PROPOSED ACTION

No adverse impact on the public can be foreseen.

1.1 Description

1.4 Decision on Proposed Action

-" Licensees authorized to possess at any one time more than one effective kilogram of special nuclear material The guide should be revised to reflect improvements in (SNM) are required in § 70.51 of 10 CFR Part 70 to techniques, to bring the guide into conformity with current establish and maintain a system of control and account practice, and to provide a list of pertinent information ability so that the standard error of any inventory difference currently available.

ascertained as a result of a measured material balance meets established minimum standards. The selection and proper

2. TECHNICAL APPROACH

application of an adequate measurement method for each of the material forms in the fuel cycle are essential for the Not applicable.

maintenance of these standards.

Many types of nondestructive assay (NDA) measurements

3. PROCEDURAL APPROACH

on SNM can involve, or even require, a high-resolution gamma ray spectroscopy system. The proposed action is to Of the alternative procedures considered, revision of the provide some general guidelines in the selection of such existing regulatory guide was selected as the most advan systems and to point out useful resources for more detailed tageous and cost effective.

information on their assembly, optimization, and use in material protection measurements.

4. STATUTORY CONSIDERATIONS

1.2 Need for Proposed Action 4.1 NRC Authority Regulatory Guide 5.9, which provides guidance in this Authority for the proposed action is derived from the area, has not been updated since 1974 and does not contain Atomic Energy Act of 1954, as amended, and the Energy a list of pertinent information currently available in the Reorganization Act of 1974, as amended, and implemented literature.

through the Commission's regulations.

1.3 Value/Impact of Proposed Action 4.2 Need for NEPA Assessment

1.3.1 NRC Operations The proposed action is not a major action that may significantly affect the quality of the human environment The experience and improvements in detector technology and does not require an environmental impact statement.

that have occurred since the guide was issued will be made available for the regulatory proces

s. Using these updated

5. RELATIONSHIP TO OTHER EXISTING OR

techniques should have no adverse impact. PROPOSED REGULATIONS OR POLICIES

1.3.2 Other Government Agencies The proposed action is one of a series of revisions of existing regulatory guides on nondestructive assay tech Not applicable. niques.

1.3.3 Industry 6. SUMMARY AND CONCLUSIONS

Since industry is already applying the more recent Regulatory Guide 5.9 should be revised to bring it up to detector technology discussed in the guide, updating these date.

techniques should have no adverse impact.

5.9-7

UNITED STATES

NUCLEAR REGULATORY COMMISSION emPST CLASS MAIL

POSTAGE FEEISPAID

WASHINGTON, D.C. 20585 USNRC

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PERMIT MeoSL

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