Regulatory Guide 3.9: Difference between revisions

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{{Adams
{{Adams
| number = ML12220A059
| number = ML003740214
| issue date = 06/30/1973
| issue date = 06/30/1973
| title = Concrete Radiation Shields
| title = Concrete Radiation Shields. Label as Withdrawn 01/15/98
| author name =  
| author name =  
| author affiliation = NRC/RES, US Atomic Energy Commission (AEC)
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
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| page count = 2
| page count = 2
}}
}}
{{#Wiki_filter:U.S. ATOMIC ENERGY COMMISSION June 1973REGULATORY GUIDEDIRECOoAT OF REGULATORY SANDARDSREGULATORY GUIDE 3.9CONCRETE RADIATION SHIELDSA. INTRODUCTIONSection 20.101 of 10 CFR Part 20, "Exposure ofIndividuals to Radiation in Restricted Areas," states thatno licensee shall possess, use, or transfer licensedmaterial in such a manner as to cause any individual in arestricted area to receive a dose in excess of the limitsspecified therein. Paragraph (c) of § 20.1 provides thatlicensees, in addition to complying with therequirements set forth in Part 20, make every reasonableeffort to maintain radiation exposures as far below thelimits specified in this part as practicable.Concrete radiation shields can be installed in nuclearfacilities such as hot laboratories, radiochemical plants,experimental facilities, and nuclear fuel fabricationplants to provide a barrier between personnel andradiation sources for the purpose cf reducing doses ofionizing radiation received by personnel to as low aspracticable levels. This guide describes practices for theconstruction of concrete radiation shielding structuresfor such nuclear facilities, which are acceptable to theRegulatory staff as methods of complying, in part, withCommission regulations with regard to reducingradiation exposures. Much of the information includedmay be applicable to shielding structures for reactorsand other nuclear and nonnuclear facilities which requireconcrete radiation shields.B. DISCUSSIONSubcommittee ANS-li, Radioactive MaterialsHandling Facilities and Specialized Equipment. of theAmerican Nuclear Society has developed a standardpresenting requirements and recommended practices forthe construction of concrete radiation shieldingstructures and for certain elements of design that relateto problems unique to this type of structure. Thisstandard was approved by the American NationalStandards Committee NIOi. Atomic Industry FacilityDesign. Construction and Operation Criteria. and it wassubsequently approved by the American NationalStandards Institute- (ANSI) on December 22. IPQ2.and designated ANSI N101.6-1972. The standarddiscusses aggregateo. design of concrete mixtures andforms, placement of concrete, design and installation ofpenetrations. embedments. metal liners, and penetrationplugs and outlines testing and quality assuranceprovisions needed to verify that the desired quality ofdesign and construction has been achieved. The standarddoes not include detailed treatments of structural designor determination of shield thickness.C. REGULATORY POSITIONThe requirements and recommended practicescontained in ANSI N101.6.1972, "Concrete RadiationShields,"' are acceptable for the construction ofradiation shielding structures for hot laboratories.radiochemical plants, experimental facilities, and nuclearfuel fabrication plants subject to the following:I. Section 2 of ANSI NI01.6-1972 lists applicabledocuments which are intended to supplement thisstandard. The specific applicability or acceptability ofthese listed documents has been or will be coveredseparately in other regulatory guides or in Commissionregulations. where appropriate.2. Section 4.8 of ANSI N101.6-1972 delineates specialprecautions to be observed in the construction ofconcrete radiation shields. Where steel or other metalsare used as aggregate t,. increase the density of theconcrete, the metal should be of such type that it willnot cause hydrogen or other explosive gases to begenerated by reaction with the cement.'Copies may be obtained from the American NuclearSociety. 244 East Ogden Avenue. Hinsdale, Illinois 60521.USAEC REGULATORY GUIDES Coe Of pubished guide may be obtaned by requem indca.ing the divisionsdesrIsd to the US. Atomic Erurgv Commission. Washington, D.C. 2054S.Regulatory Guides or ISS*ed to describe ed mke lvwoiill4 to the public Atitenteio Director Of Regulatory Standards. Comnments and sol 1tions formenhods accepatmle to she AEC Regulatory staff of Imifes owtong specific parts of inovernwts in these guides oe encouraged and should be sent to the Secretarythe Comone.on5 -egat.:at1Os. CdP'isefe te-hrouee used by the seff in of the Commoonso. US. Atomic Energy Commssion. Washington. D.C. evaluating spec:fic ioblems 4; postulated eaecklnts. or to pro-ide guidance to Atlefstion: Chief. Public Staff.Ii**cnts. ReapulgO ry Guides not substitutes fw regulations end cooslaei swith them .not required. Methods and iolutions differenit from thoe at out in The guides ae issue in the following ten broad divisions:the ill b4 acceptable if they porovde b at for this findings tothe resuano or continuance of a permit or Oicene by the Commisson. 1. Power Reactors 6. Produacts2 Reseach end Test Reac ors 7. Transoortation3. Fuels an Mt erials Facilities a. HelthPubli'shad guides will be revised eiw.odimi. w appropriate, to acornmndsa 4. siting g. Antitrust Revieweninnent, and to reflect now informa~tion or eUperleis 5. Matarials end Plant Protection 10. General 3. Section 6.4 of ANSI NIOi.6-1972 does not explainhow some of" the variables which are used in theequations for bending moment and tensile stress are tobe determined. Therefore this section should not be usedas a substitute for detailed thermal stress analysis in thedesip of temperature reinforcement for control ofcracking in specific concrete radiation shields.4. Section 8.7.1 of ANSI Ni0i.6-1972 states, in part.that reinforcing steel or other means. be provided fortransferring shear forces through a construction joini.This requirement is not sufficient. Provision should bemade for adequate means of transferring shear and otherforces through the joint.N'3.9-2}}
{{#Wiki_filter:U.S. ATOMIC ENERGY COMMIIISION
REGULATORY
DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 3.9 CONCRETE RADIATION SHIELDS
 
==A. INTRODUCTION==
Section 20.101 of 10 CFR Part 20. "Exposure of Individuals to Radiation in Restricted Areas," states that no licensee shall possess. use, or transfer licensed material in such a manner as to cause any individual in a restricted area to receive a dose in excess of the limits specified therein. Paragraph (c) of § 20.1 provides that licensees, in addition to complying with the requirements set forth in Part 20. make every reasonable effort to maintain radiation exposures as far below the limits specified in this part as practicable.
 
Concrete radiation shields can be installed in nuclear facilities such as hot laboratories, radiochemical plants, experimental facilities, and nuclear fuel fabrication plants to provide a barrier between personnel and radiation sources for the purpose cf reducing doses of ionizing radiation received by personnel to as low as practicable levels. This guide describes practices for the construction of concrete radiation shielding structures for such nuclear facilities, which are acceptable to the Regulatory staff as methods of complying, in part, with Commission regulations with regard to reducing radiation exposures. Much of the information included may be applicable to shielding structures for reactors and other nuclear and nonnuclear facilities which require concrete radiation shields.
 
==B. DISCUSSION==
Subcommittee ANS- I,  
Radioactive Materials Handling Facilities and Specialized Equipment. of the American Nuclear Society has developed a standard presenting requirements and recommended practices for the construction of concrete radiation shielding structures and for certain elements of design that relate to problems unique to this type of structure. This standard was approved by the American National Standards Comrruttee N]01. Atomic Industry Facility June 1973 GUIDE
Deipi. Construction and Operation Criteria. and it was subsequently approved by the American National Standards Institute (ANSI I on December 2'Z.
 
1Q'".
and designated ANSI  
NIOI.6.1Q72.
 
The standard discusses agpegate,. design of concrete mixtures and forms, placement of concrete, design and installatior of penetrations. embedments. metal liners, and penetration plup and outlines testing and quality assurance provistions needed to verify that the desired quality of design and construction has been achieved. The standard does not include detailed treatments of structural design or determination of shield thickness.
 
==C. REGULATORY POSITION==
The requirements and recommended practices contained in ANSI N101.6-1972. "Concrete Radiation Shields,"'  
are acceptable for the construction of radiation shielding structures for hot laboratories.
 
radiochemical plants, experimental facilities, and nuclear fuel fabrication plants subject to the, following:  
I. Section 2 of ANSI NI01.6-1q712 lists applicable documents which are intended to supplement this standard. The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations. where appropriate.
 
2. Section A.8 of ANSI N1OI..-Q072 delineates special precautions to be observed in the construction of concrete radiation shields. Where steel or other metals are used as aggrepte t, increase the density of the concrete. the metal should be of such type that it will not cause hydrogen or other explosive gases to be generated by reaction with the cement.
 
'Copies may be obtained from the Ameri.-can Nuclear Society. 244 Eait Ogden Avenue. Hinsiale. litanois 60521.
 
USAEC REGULATORY GUIDES  
CSS
Of Pub e
gdnie, n*v be obtained by remterl i nd,cing d",o
"a.wd to the US. Atomic Emwrv Comm.es-on.
 
Wmshnpoo. DC. 20546.
 
Rqulato'v Guofdt we
,uuod to delwbe end Rieke 8*labd to the pihdic A=I..of Otuo. of Re*fteiarv Stendm Cortoivnts end sualutsm~
fo twhot~ &cmouO'e to the AEC fteiujtetolv Staff of irrvifivenwuuiti toectac Part of iff aiiiefem A thewe gusda wr# owtoOusagd and thouid be Sent to the Secwemiey th Zp
ý.r I :e;;4.o*t.
 
-- 00--0400
Mrtwinwn uedb the Staff An of thte Cosmtmiuoi. US, Atomic ErAwvy Commission, Wah-nton. 0.C. 2064S.
 
owludninig qWeatic ptoWnn 0' or 0tsU~tmd SimiWTS. of to Provid gu.diNo to Atlefltcf t.N4.P~b P,eVoCit*fl StAff.
 
go.mnnts Regulatory Q.u.dmarl roW tflO4 uuttis for rgltio~ns end con wiiiin
-t their".  
io requied 0010V
and solurlim different fromn than. wrt out m The gwdw 01 -uied - the fo4Imy.'q ten b'old dmrsionl the, guide
,11t e acceptable 4 they -0M
a bMIG fo th fidni
"W t the muiax or cor~nuem of a pens~
or honotO bv the ComN"wo I Pom filieton
 
===6. Productt ===
2 Aeftewo and Test Rea ots
7, TItooef*ol1
3. Fu end Mater,.
 
====t. Fecatitm ====
9, Occuar.outa Hfeafth Pa*,doheisd gudi wiall bel rteat1d CS.Odiomdtii.
 
" boovitoonte to eceofnsmsedetg
4 Ettwotn"Wrtal 8,d 5.tq S Artlt,..tt ft.,...mi CC`,i"`"lns and to refer tact .-
forrAliiOrt OXCOWWtana
6 matwterw and pis"lant Prt.ort~  
10 G~81a
 
3.
 
Section 6.4 of ANSI N I0 .6-1972 does not explain how some d" the variables which are used in the equations for bending moment and tensle strew am to be determined. Therefore this section should not be used as a substitute for detailed thermal stres analysis in the desigp of temperature reinforcement for control of aacking in specific concrete radiation shields.
 
4.
 
Section 8.7.1 of ANSI NIOI.6-1972 sutes, in part.
 
that rednforcli steel or other means, be provided for tVan erring shoa forces throuOh a wonstructien joint.
 
This requirement Is not sufficient. Provision skould be made for adequaste meam of transferring shear and other forces through the joint.
 
?C'' '
3.9.2}}


{{RG-Nav}}
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Latest revision as of 02:06, 17 January 2025

Concrete Radiation Shields. Label as Withdrawn 01/15/98
ML003740214
Person / Time
Issue date: 06/30/1973
From:
Office of Nuclear Regulatory Research
To:
References
RG-3.009
Download: ML003740214 (2)


U.S. ATOMIC ENERGY COMMIIISION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

REGULATORY GUIDE 3.9 CONCRETE RADIATION SHIELDS

A. INTRODUCTION

Section 20.101 of 10 CFR Part 20. "Exposure of Individuals to Radiation in Restricted Areas," states that no licensee shall possess. use, or transfer licensed material in such a manner as to cause any individual in a restricted area to receive a dose in excess of the limits specified therein. Paragraph (c) of § 20.1 provides that licensees, in addition to complying with the requirements set forth in Part 20. make every reasonable effort to maintain radiation exposures as far below the limits specified in this part as practicable.

Concrete radiation shields can be installed in nuclear facilities such as hot laboratories, radiochemical plants, experimental facilities, and nuclear fuel fabrication plants to provide a barrier between personnel and radiation sources for the purpose cf reducing doses of ionizing radiation received by personnel to as low as practicable levels. This guide describes practices for the construction of concrete radiation shielding structures for such nuclear facilities, which are acceptable to the Regulatory staff as methods of complying, in part, with Commission regulations with regard to reducing radiation exposures. Much of the information included may be applicable to shielding structures for reactors and other nuclear and nonnuclear facilities which require concrete radiation shields.

B. DISCUSSION

Subcommittee ANS- I,

Radioactive Materials Handling Facilities and Specialized Equipment. of the American Nuclear Society has developed a standard presenting requirements and recommended practices for the construction of concrete radiation shielding structures and for certain elements of design that relate to problems unique to this type of structure. This standard was approved by the American National Standards Comrruttee N]01. Atomic Industry Facility June 1973 GUIDE

Deipi. Construction and Operation Criteria. and it was subsequently approved by the American National Standards Institute (ANSI I on December 2'Z.

1Q'".

and designated ANSI

NIOI.6.1Q72.

The standard discusses agpegate,. design of concrete mixtures and forms, placement of concrete, design and installatior of penetrations. embedments. metal liners, and penetration plup and outlines testing and quality assurance provistions needed to verify that the desired quality of design and construction has been achieved. The standard does not include detailed treatments of structural design or determination of shield thickness.

C. REGULATORY POSITION

The requirements and recommended practices contained in ANSI N101.6-1972. "Concrete Radiation Shields,"'

are acceptable for the construction of radiation shielding structures for hot laboratories.

radiochemical plants, experimental facilities, and nuclear fuel fabrication plants subject to the, following:

I. Section 2 of ANSI NI01.6-1q712 lists applicable documents which are intended to supplement this standard. The specific applicability or acceptability of these listed documents has been or will be covered separately in other regulatory guides or in Commission regulations. where appropriate.

2. Section A.8 of ANSI N1OI..-Q072 delineates special precautions to be observed in the construction of concrete radiation shields. Where steel or other metals are used as aggrepte t, increase the density of the concrete. the metal should be of such type that it will not cause hydrogen or other explosive gases to be generated by reaction with the cement.

'Copies may be obtained from the Ameri.-can Nuclear Society. 244 Eait Ogden Avenue. Hinsiale. litanois 60521.

USAEC REGULATORY GUIDES

CSS

Of Pub e

gdnie, n*v be obtained by remterl i nd,cing d",o

"a.wd to the US. Atomic Emwrv Comm.es-on.

Wmshnpoo. DC. 20546.

Rqulato'v Guofdt we

,uuod to delwbe end Rieke 8*labd to the pihdic A=I..of Otuo. of Re*fteiarv Stendm Cortoivnts end sualutsm~

fo twhot~ &cmouO'e to the AEC fteiujtetolv Staff of irrvifivenwuuiti toectac Part of iff aiiiefem A thewe gusda wr# owtoOusagd and thouid be Sent to the Secwemiey th Zp

ý.r I :e;;4.o*t.

-- 00--0400

Mrtwinwn uedb the Staff An of thte Cosmtmiuoi. US, Atomic ErAwvy Commission, Wah-nton. 0.C. 2064S.

owludninig qWeatic ptoWnn 0' or 0tsU~tmd SimiWTS. of to Provid gu.diNo to Atlefltcf t.N4.P~b P,eVoCit*fl StAff.

go.mnnts Regulatory Q.u.dmarl roW tflO4 uuttis for rgltio~ns end con wiiiin

-t their".

io requied 0010V

and solurlim different fromn than. wrt out m The gwdw 01 -uied - the fo4Imy.'q ten b'old dmrsionl the, guide

,11t e acceptable 4 they -0M

a bMIG fo th fidni

"W t the muiax or cor~nuem of a pens~

or honotO bv the ComN"wo I Pom filieton

6. Productt

2 Aeftewo and Test Rea ots

7, TItooef*ol1

3. Fu end Mater,.

t. Fecatitm

9, Occuar.outa Hfeafth Pa*,doheisd gudi wiall bel rteat1d CS.Odiomdtii.

" boovitoonte to eceofnsmsedetg

4 Ettwotn"Wrtal 8,d 5.tq S Artlt,..tt ft.,...mi CC`,i"`"lns and to refer tact .-

forrAliiOrt OXCOWWtana

6 matwterw and pis"lant Prt.ort~

10 G~81a

3.

Section 6.4 of ANSI N I0 .6-1972 does not explain how some d" the variables which are used in the equations for bending moment and tensle strew am to be determined. Therefore this section should not be used as a substitute for detailed thermal stres analysis in the desigp of temperature reinforcement for control of aacking in specific concrete radiation shields.

4.

Section 8.7.1 of ANSI NIOI.6-1972 sutes, in part.

that rednforcli steel or other means, be provided for tVan erring shoa forces throuOh a wonstructien joint.

This requirement Is not sufficient. Provision skould be made for adequaste meam of transferring shear and other forces through the joint.

?C '

3.9.2