Letter Sequence Other |
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EPID:L-2022-DOT-0007, E-61283 Enclosure 5, Orano NPS Statement of Proprietary Information for the Application for the Validation Request for the FCC-3 Package (Approved, Closed) |
Results
Other: ML22271A186, ML22271A189, ML22271A190, ML22271A450, ML22271A452, ML22271A454, ML22271A455, ML22271A458, ML22271A460, ML22271A461, ML22271A463, ML22271A465, ML22271A466, ML22271A468, ML22271A470, ML22271A471, ML22271A472, ML22271A474, ML22271A476, ML22271A477, ML22271A479, ML22271A481, ML22271A482, ML22271A484, ML22271A486, ML22271A487, ML22271A636, ML22271A637, ML22271A638, ML22271A639, ML22271A640, ML22271A641, ML22271A642, ML22271A643, ML22271A644, ML22271A645, ML22271A646, ML22271A647, ML22271A648, ML22271A649, ML22271A650, ML22271A675, ML22271A677, ML22271A678, ML22271A686, ML22271A688, ML22271A790, ML22271A791, ML22271A792, ML22271A793... further results
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MONTHYEARML22271A6411998-08-19019 August 1998
E-61283 Enclosure 4, 009h1 Ap 2.1-8 TFXDC2108EN Npv, Revision B, Modified RCC Container - Proto 2 - Regulatory Test Programme (Public)
Project stage: Other
ML22271A6392004-05-0404 May 2004
E-61283 Enclosure 4, 009G1 AP 2.1-7 TFXEDC2104-NPV, Rev. E, Modification of FCC Containers Choice of Prototype 2 Drop Configurations for Regulatory Tests (Public)
Project stage: Other
ML22271A8002004-10-29029 October 2004
E61283, Enclosure 4, 013c1 Appendix 2.5-3, Document No. FF/DC/01106 Revision a, E0, Safety/Criticality Study of FCC3v2 Containers 14 X 14 8 Foot and 14 X 14 10 Foot Assemblies (Public)
Project stage: Other
ML22271A8022007-12-19019 December 2007
E61283, Enclosure 4, 013d1 Appendix 2.5-4, FF DC 04191, Revision B, Safety/Criticality Study for FCC4 Packages & 17x17XL Assemblies Justification for an Increased Cavity Cross Section (Public)
Project stage: Other
ML22271A6462009-01-0101 January 2009
E-61283 Enclosure 4, 009c1 Ap 2.1-3 Document No. NTC-08-00135891E-NPV, Revision No. 01E, Analysis of the Fatigue Strength of the FCC3/FCC4 Containers (Public)
Project stage: Other
ML22271A4702009-05-0101 May 2009
E-61283 Enclosure 4, 009a1 Appendix 2.1-1, FFDC05090-A EN Npv, FCC3 Containers - Lashing Diagrams (Public)
Project stage: Other
ML22271A8162009-06-27027 June 2009
E-61283 Enclosure 4, 010d1 Appendix 2.2-4, NTC-08-00118662E-NPV, Rev. 1E, Note on the Characterization of Resin Fs 69
Project stage: Other
ML22271A6442010-07-0101 July 2010
E-61283 Enclosure 4, 009b1 Ap 2.1-2 F2, Document No. NEEL-F 2008 DC 117EN, Revision B, FCC3 Containers for Fresh Fuel Assemblies Data for the Fatigue Strength Analysis of the Lifting Boxes and Upper Shell (Public)
Project stage: Other
ML22271A8152012-04-0202 April 2012
E-61283 Enclosure 4, 010d Appendix 2.2-4 DOS-13-00081778-204-NPV, Rev. 00, Reference to 10373-B-1, Revision 3, Summary Note on the Characterization of Fs 69 Resin
Project stage: Other
ML22271A4772012-04-30030 April 2012
E-61283 Enclosure 4, 002a Appendix 1.3-1,Document No. DOS-13-00081779-031-NPV, Revision 00, Appendix 1.3-1 - Description of Fuel Rod Boxes for FCC3 Containers (Public)
Project stage: Other
ML22271A6432012-04-30030 April 2012
E-61283 Enclosure 4, 009j Ap 2.1-10 DOS-13-00081778-110-NPV, Revision 00, Container Prototype No. 2, Drop Test Report (Public)
Project stage: Other
ML22271A6422012-04-30030 April 2012
E-61283 Enclosure 4, 009i Ap 2.1-9 DOS-13-00081778-109-NPV, Revision 00, Container Prototype No. 1, Drop Test Report (Public)
Project stage: Other
ML22271A6402012-04-30030 April 2012
E-61283 Enclosure 4, 009h Ap 2.1-8 DOS-13-00081778-108-NPV, Revision 00, Modified RCC Container - Prototype 2 - Regulatory Test Programme (Public)
Project stage: Other
ML22271A6382012-04-30030 April 2012
E-61283 Enclosure 4, 009g Ap 2.1-7 DOS-13-00081778-107-NPV, Modification of RCC Containers - Selection of Drop Configurations for Prototype 2 in the Context of Regulatory Tests (Public)
Project stage: Other
ML22271A4842012-04-30030 April 2012
E-61283 Enclosure 4, 002d Appendix 1.3-4, Document No. DOS-13-00081778-034-NPV, Revision 00, Appendix 1.3-4 - Test Report Leaching of Enriched Reprocessed Uranium (Eru) Pellets (Public)
Project stage: Other
ML22271A4792012-04-30030 April 2012
E-61283 Enclosure 4, 002b Ap 1.3-2 DOS-13-00081779-032-NPV, Revision 00, Appendix 1.3-2 - Drawing of Fuel Rod Boxes for FCC3 Containers (Public)
Project stage: Other
ML22271A4712012-04-30030 April 2012
E-61283 Enclosure 4, 009b Appendix 2.1-2, Document No. DOS-13-00081779-102-NPV, Revision 00, FCC3 Containers for Fresh Fuel Assemblies – Data for Fatigue Resistance Analysis of Lifting Boxes and Upper Shell (Public)
Project stage: Other
ML22271A4682012-04-30030 April 2012
E-61283 Enclosure 4, 009a Appendix 2.1-1, Document No. DOS-13-00081779-101-NPV, Revision 00, Table of Contents, FCC3 Containers - Tie-down Diagrams, Areva (Public)
Project stage: Other
ML22271A4542012-04-30030 April 2012
E-61283 Enclosure 4, 003d Appendix 1.4-4, Document No. DOS-13-00081779-044-NPV, Revision 00, Table of Contents, Photographs of the FCC3 Package (Public)
Project stage: Other
ML22271A4522012-04-30030 April 2012
E-61283 Enclosure 4, 003c Appendix 1.4-3, Document No. DOS-13-00081778-043-NPV, Revision 00, Table of Contents, Summary of Toughness Tests
Project stage: Other
ML22271A8012012-09-0303 September 2012
E61283, Enclosure 4, 013d Appendix 2.5-4 (FCC3-FCC4), DOS-13-00081778-504-00-NPV, Rev. 00, Reference to Ffdc 04191, Rev. B, Safety/Criticality Study for FCC4 Packages and 17x17 Xl Assemblies Justification for an Increased Cavity Cross Secti
Project stage: Other
ML22271A4502012-09-30030 September 2012
E-61283 Enclosure 4, 003b Appendix 1.4-2. Document No. DOS-13-00081779-042-NPV, Revision 1, Drawings of the FCC3 Package, Version 2 (Public)
Project stage: Other
ML22271A6452013-04-30030 April 2013
E-61283 Enclosure 4, 009c Ap 2.1-3, Document No. DOS-13-00081778-103-NPV, Revision 00, Analysis of the Fatigue Behaviour of FCC3/FCC4 Containers, Tn International Document (Public)
Project stage: Other
ML22271A7902016-03-31031 March 2016
E-61283 Enclosure 4, 010e Appendix 2.2-5, Document No. DOS-13-00081778-205-NPV, Revision 00, Safety / Criticality Study of FCC3 and FCC4 Containers – Transport of Fuel Rods in Boxes (Public)
Project stage: Other
ML22271A8092017-09-0101 September 2017
E-61283 Enclosure 4, 009m Ap 2.1-13 DOS-13-00081778-113-NPV, Revision 2, Appendix 2.1-13 Complimentary Analysis of FCC Package Behaviour in Accidental Drop Conditions (Public)
Project stage: Other
ML22271A6372021-10-0808 October 2021
E-61283 Enclosure 4, 009f1 Ap 2.1-6 FFDC04223-EN Npv Revision 4.0, Transportation in FCC Container Mechanical Aspects Related to a Change in the Fuel Assembly Materias (Public)
Project stage: Other
ML22271A7992022-04-29029 April 2022
E-61283, Enclosure 4, 013c Appendix 2.5-3, Document No. DOS-13-00081778-503-NPV, Revision 00, Reference Document No. Ffdc 01106, Rev. a, Criticality-safety Analysis of FCC3 Containers Version 2 – Assembly Types 14x14 8-foot and 14x14 10-foo
Project stage: Other
ML22271A1902022-05-10010 May 2022
E-61283 Enclosure 2, Certificate of the French Competent Authority F/347/AF-96 (Gy), FCC-3 Transport Package (French Version) (Public)
Project stage: Other
ML22271A1892022-05-10010 May 2022
E-61283 Enclosure 1, Certificate of the French Competent Authority F/347/AF-96 (Gy), FCC-3 Transport Package (English Version)
Project stage: Other
ML22271A6502022-05-13013 May 2022
E-61283 Enclosure 4, 009e1 Ap 2.1-5, Framatome, Document No. D02-ARV-01-186-616, Revision a, FCC 3 - Containers for Fresh Fuel Assemblies - Stacking Behaviour (Non-proprietary)
Project stage: Other
ML22271A4742022-05-16016 May 2022
E-61283 Enclosure 4, DOS-19-021165-001-NPV, Version 2.0, Chapter 1.2, Administrative Information (Public)
Project stage: Other
ML22271A8072022-05-18018 May 2022
E-61283 Enclosure 4, 009k Appendix 2.1-11, Document No. DOS-19-021165-011-NPV, Version 1.o, Justification of the Performance of the FCC3 Shell Fasteners During a 9m Vertical Drop (Public)
Project stage: Other
ML22271A4762022-05-18018 May 2022
E-61283 Enclosure 4, 002 DOS-19-021165-002-NPV, Chapter 1.3, Specifications Relating to Radioactive Content (Public)
Project stage: Other
ML22271A4822022-06-0303 June 2022
E-61283 Enclosure 3, 002c1 Ap 1.3-3 Dwg FFDC05098-EN Npv, Revision 3.0, STR - Study Report (Public)
Project stage: Other
ML22271A1862022-07-21021 July 2022
E-61283 Enclosure 6, Document No. DOS-18-016471-000, Versions 1.0 and 5.0, Summary of Changes Between Version 1.0 to Version 2.0 for Safety Analysis Report for FCC-3 (File: Nte 22-005637-000-2.0-FCC3) (Public)
Project stage: Other
ML22271A4552022-08-0202 August 2022
E-61283 Enclosure 4, 003e Appendix 1.4-5, Document No. DOS-19-021166-010-NPV, Revision 0, Analysis of the Ageing Mechanisms of the Fcc3 and FCC4 Package Models (Public)
Project stage: Other
ML22271A1842022-08-0202 August 2022
E-61283 Enclosure 5, Orano NPS Statement of Proprietary Information for the Application for the Validation Request for the FCC-3 Package
Project stage: Request
ML22271A8082022-08-0303 August 2022
E-61283 Enclosure 4, 009l Appendix 2.1-12 DOS-13-00081778-112-NPV, Rev. 1, Appendix 2.1-12 FCC Packaging Rod Boxes - Proof of the Mechanical Strength of Box Equipment (Public)
Project stage: Other
ML22271A7942022-08-0303 August 2022
E-61283 Enclosure 4, 013a Appendix 2.5-1, Document No. DOS-19-021165-015-NPV, Version 1.0, Safety Analysis Report (Public)
Project stage: Other
ML22271A8102022-08-0303 August 2022
E-61283 Enclosure 4, 009n Appendix 2.1-14 DOS-19-021165-012-NPV, Version 1.0, Variation in the Mechanical Properties of Shell and Screw Steels Between 40°C …(Public)
Project stage: Other
ML22271A8122022-08-0303 August 2022
E-61283, Enclosure 4, 010a Appendix 2.2-1, DOS-19-021165-018-NPV, Version 1.0, Reference to D02-ARV-01-198-455 (Translation of D02-ARV-01- 167-814), Justification by Cfd Simulation of the Thermal Behavior of the FCC Container
Project stage: Other
ML22271A8132022-08-0303 August 2022
E-61283, Enclosure 4, 010a1 Ap 2.2.1 FFP_D02-ARV-01-198-455, Revision a, Justification by CFO Simulation of the Thermal Behavior of the FCC Container; Replacing Former Chapters 2.2-1 (Pved DC 04 055) and 2.2-2 (NEPL-F 2018 DC 152) (Public)
Project stage: Other
ML22271A8142022-08-0303 August 2022
E-61283 Enclosure 4, 010c Appendix 2.2-3, FS1-0062270, Rev. 1 (DOS-18-016472-017 (En), Rev. 1), Behavior of Rod Made of M5 Framatome or Zircaloy-4 Alloy Subjected to the IAEA Thermal Test in FCC Packaging (Public)
Project stage: Other
ML22271A1882022-08-0303 August 2022
E-61283, Transmittal Letter from Orano to DOT, Application for Validation of French Competent Authority Certificate F/347/AF-96 for Model No. FCC-3 Transport Package
Project stage: Request
ML22271A8112022-08-0303 August 2022
E-61283 Enclosure 4, 010 Chapter 2.2, Document No. DOS-19-021165-013-NPV, Version 1.0, Thermal Analysis (New Reference DOS-19-021165-013, Revision 1.0) (Public)
Project stage: Other
ML22271A7912022-08-0303 August 2022
E-61283 Enclosure 4, 010f Appendix 2.2-6 Document No. DOS-13-00081778-206-NPV, Revision 0, Thermal Behaviour of the FCC Packaging Under Normal Conditions of Transport (Public)
Project stage: Other
ML22271A8062022-08-0303 August 2022
E-61283 Enclosure 4, 013f, Appendix 2.5-6, Document No. FFDC00561EN, Criticality Safety Study-Fresh UO2 Fuel Transportation casks-Determining the Uncertainties Using Cristal, Revision 4 (Public)
Project stage: Other
ML22271A7972022-08-0303 August 2022
E-61283 Enclosure 4, 013b Appendix 2.5-2, Document No. DOS-19-021165-016-NPV, Version 1.0, Safety Analysis Report-Reference Ffdc 01046 E0, Version 3.0, Safety/Criticality Study of FCC3 and FCC4 Containers –Transport of Fuel Rods in Boxes (P
Project stage: Other
ML22271A7922022-08-0303 August 2022
E-61283 Enclosure 4, 012 Appendix 2.4, Document No. DOS-13-00081778-400, Revision 1, Analysis of External Dose Rates (Public)
Project stage: Other
ML22271A7932022-08-0303 August 2022
E-61283 Enclosure 4, 013 Chapter 2.5, Version 1, Document No. DOS-19-021165-014-NPV, Safety Analysis Report-Criticality-Safety Analysis (Public)
Project stage: Other
2013-04-30
[Table View] |
Text
Non-proprietary version Form: PM04-4-MO-6 Rev. 00 AREVA TN AREVA UNRESTRICTED DISTRIBUTION NUCLEAR LOGISTICS OPERATIONS APPENDIX 2.2-6 THERMAL BEHAVIOUR OF THE FCC PACKAGING UNDER NORMAL CONDITIONS OF TRANSPORT SAFETY ANALYSIS REPORT FCC3 - FCC4 Prepared by Identification DOS-13-00081778-206-NPV Checked by Rev.
00 Page 1 / 12 TN International TableofContents Revisionshistory 2
- 1. Introduction 3
- 2. Calculationsapproachandmethods 3
- 3. Results 4
- 4. Conclusion 6
- 5. References 6
Listoffigures 8
Listoftables 11
A AREVA
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206-NPV Rev.:
00 Page 2 of 12 Non-proprietary version Revisions history Rev.
Date Purpose and record of changes Prepared by / Checked by 0
First issue I I
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206-NPV Rev.:
00 Page 3 of 12 Non-proprietary version
- 1.
Introduction The purpose of this analysis is to evaluate, using numerical calculations, the temperature of the FCC packaging under Normal Conditions of Transport (NCT)
- 2.
Calculations - approach and methods 2.1.
Software The calculations are carried out using the I-DEAS software interfaced with the thermal module TMG <1>.
2.2.
Model mesh & geometry The model used in this study is a 2D thermal model, representing a section of the uninterrupted section of the FCC4 packaging shell and internal fittings. The model details the plates, the resin of the frame and the doors, the fuel rod claddings, the guide tubes and the pellets, as per the models presented in Appendix 2.2-1.
As in Appendix 2.2-1, the sizes of the air inlet openings in the cavity of the internal fittings are, respectively, 7mm in the upper section and 5 mm in the lower.
The 17x17 rod array is represented in the calculation model. The geometry and meshing of the internal fittings and17x17 fuel rod array is presented in figure 1.
The geometry of the shell is modelled in accordance with drawing <2> in Appendix 1.4-1 of Chapter 1.4. As per this drawing, the outer radius of the upper shell is mm, the outer radius of the lower shell is mm. The calculation model also represents the air between the internal fittings and the packaging shell.
2.3.
Materials The characteristics of the materials used for the packaging, and the air, are given in tableau
- 1.
2.4.
Power levels The fresh UO2 pellets do not emit any power.
2.5.
Heat exchanges 2.5.1.
Conduction The conductive exchanges within the materials are calculated directly by the code <1>,
using the thermal conductivity of each material, given in Table tableau 1.
The gap between the claddings and the pellets is calculated using the geometric characteristics of the 17x17 array, taken from Chapter 2.2-1, and listed in the table below:
dC: External rod diameter (mm) e:
Thickness of claddings (mm) dP: Pellet diameter (mm)
Array pitch (mm) 12.6 The radial gap (noted j) between the claddings and the pellets is calculated using the following equation:
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206-NPV Rev.:
00 Page 4 of 12 Non-proprietary version
2 for the 17x17 array.
The Contact Resistance value (Rc) is deduced using the equation:
Where helium = W.m-1.K-1. from tableau 1 Therefore, the contact resistance for a 17x17 array is as follows:
. /
2.5.2.
Convection The air surrounding the packaging shell is not represented. The heat exchanges, by convection, are modelled, using a coefficient of exchange: h = 1.4T1/3 W.m-2.K-1. The calculation is based upon correlations taken from <3>.
2.5.3.
Radiation
The radiative exchanges between the claddings and the plates of the internal fittings, and between the outer surface of the internal fittings and the shell of the packaging, are directly calculated using the code <1>. They are modelled using radiative boxes. The emissivity levels of the various materials are given in Table 1.
Radiative exchanges between the outer surfaces of the shell and the ambient air are modelled using a view factor of 1. The shell is covered, inside and out, with a paint coating, the emissivity of which is (conservative value from Appendix 2.2-1).
2.5.4.
Ambient The temperature of the ambient air is assumed to be 38°C.
2.5.5.
Exposure to sunlight The calculation is carried out for transient operating conditions with 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of sunlight exposure per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. (regulatory exposure over 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> followed by zero exposure for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />). The exposure is defined below, as per Table 13 of
<4>:
The solar flux received by the upper (curved) section of the packaging shell is 400 W/m².
The solar flux received by the vertical walls and lower (curved) section of the packaging shell is 200 W/m².
The density of the solar flux received by a given surface is, where is the surface absorptivity and E the regulatory sunlight.
The absorptivity is conservatively considered as being equal to 1 (See tableau 1)
- 3.
Results
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206-NPV Rev.:
00 Page 5 of 12 Non-proprietary version The following table gives the maximum temperatures reached by the shell and packaging in steady state transient operating conditions.
Structure Temperature Time Shell Tmax = °C 43,200 s External plates Tmax = °C 43,210 s Resin Tmax = °C Tavg max = °C 43,230 s 43,500 s Internal plates Tmax = °C 44,100 s Claddings Tmax = °C 44,100 s The figure below shows the changes in the maximum temperatures of the various components making up the packaging.
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206-NPV Rev.:
00 Page 6 of 12 Non-proprietary version The figure below shows the range of packaging temperatures at the moment the temperature of the external plates of the doors on the internal fittings is maximum.
- 4.
Conclusion The maximum temperatures reached by the main components making up the FCC packaging under Normal Conditions of Transport and regulatory sunlight exposure are as follows:
External shell of the packaging, Tmax = °C, External plates of the internal fittings, Tmax = °C, Resin within the internal fittings, Tmax = °C, Fuel rod claddings, Tmax = °C.
- 5.
References
<1> Finite element calculation software NX I-DEAS 6.1 M1 interfaced with the thermal model TMG 6.0.1181 distributed by Siemens PLM software.
<2> Drawing of the FCC4 packaging with its shell, entitled: Container for two UO2 fuel assemblies, 14-foot model - 17 x 17 (Type XL and EPR) and reference 229 K 0602.
<3> Handbook of Transfer Fundamentals - W.M. ROHSENOW, J.P. HARTNETT, E.N. GANIC, Mc Graw Hill - 2nd Edition
<4> Regulations for the Safe Transport of Radioactive Materials - Requirements N° SSR 6 - at the revision indicated in Chapter 1.2.
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
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<5> Archiving CDE3040600 / Thermique / CAL-13-00078918-002-00 Model: FCC4_coque.
Part FE model FE study Description 2D model Basic configuration TRANSIENT 2D model of the FCC4 packaging in the shell, for thermal calculations under transient operating conditions
Form: PM04-4-MO-6 Rev. 00 AREVA UNRESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
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00 Page 8 of 12 Non-proprietary version List of figures Figure Title Number of pages 1
Geometry of the internal fittings and array of fuel rods (17x17) for the FCC4 packaging 1
2 Meshing of the internal fittings and array of fuel rods (17x17) for the FCC4 packaging 1
TOTAL 2
Form: PM04-4-MO-6 Rev. 00 AREVA RESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
DOS-13-00081778-206 Rev.:
00 Page 9 of 12 Non-proprietary version GEOMETRY OF THE INTERNAL FITTINGS AND ARRAY OF FUEL RODS (17X17) FOR THE FCC4 PACKAGING GEOMETRY OF THE INTERNAL FITTINGS:
GEOMETRY OF THE FUEL ROD ARRAY (17X17)
LU O::'.
- J C)
LL
Form: PM04-3-MO-3 Rev. 2 AREVA RESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
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00 Page 10 of 12 Non-proprietary version MESHING OF THE INTERNAL FITTINGS AND ARRAY OF FUEL RODS (17X17) FOR THE FCC4 PACKAGING N
w 0::::
- J C)
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00 Page 11 of 12 Non-proprietary version List of tables Table Title Number of pages 1
Properties of the materials used in the FCC4 packaging 1
TOTAL 1
Form: PM04-3-MO-3 Rev. 2 AREVA RESTRICTED DISTRIBUTION AREVA TN NUCLEAR LOGISTICS OPERATIONS Identification:
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00 Page 12 of 12 Non-proprietary version THERMAL PROPERTIES OF THE MATERIALS USED IN THE FCC4 PACKAGING Material Thermal conductivity (W m-1 K-1)
Specific heat Cp (J/kg K)
Den sity (kg/m3)
Emissivity Solar absorptivity Stainless steel 20°C 14.71 500 7800 1
200°C 17.30 Resin Zy-4 claddings 20°C 20°C 200°C 200°C UO2 20°C 9.9 20°C 234.6 10.410 200°C 7.1 200°C 277.8 Air 20°C 0.0256 1,150 200°C 0.0385 Helium 0.33 5.190 3.28
- The thermal inertia of air is ignored.
TABLEAU 1