ML22063B115
| ML22063B115 | |
| Person / Time | |
|---|---|
| Site: | 07103036 |
| Issue date: | 12/31/2021 |
| From: | Kyoto Univ |
| To: | Office of Nuclear Material Safety and Safeguards |
| Bernie White NMSS/DFM/STL 301-415-6577 | |
| Shared Package | |
| ML22063B110 | List: |
| References | |
| EPID L-2020-DOT-0000 | |
| Download: ML22063B115 (90) | |
Text
SAFETY ANALYSIS REPORT OF JRF-90Y-950K 2021 Kyoto University
CONTENTS Page
() Description of nuclear fuel package ************************** ()
A. Purpose and conditions *************************************** ()--1 B. Kinds of package ********************************************* ()--1 C. Packaging **************************************************** ()--1 D. Contents of packaging **************************************** ()--1
() Safety analysis of nuclear fuel package ********************** ()
A. Structural analysis ****************************************** ()--1 A.1 Structural design ****************************************** ()--1 A.1.1 General description ************************************* ()--1 A.1.2 Design standards **************************************** ()--2 A.2 Weight and center of gravity ******************************* ()--33 A.3 Mechanical properties of materials ************************* ()--33 A.4 Requirements of the package ******************************** ()--50 A.4.1 Chemical and electrical reactions *********************** ()--50 A.4.2 Low temperature strength ******************************** ()--51 A.4.3 Sealing device ****************************************** ()--52 A.4.4 Hoisting accessory ************************************** ()--53 A.4.5 Tightening device *************************************** ()--58 A.4.6 Pressure ************************************************ ()--66 A.4.7 Vibration *********************************************** ()--68 A.5 Normal test conditions ************************************* ()--71 A.5.1 Thermal test ******************************************** ()--71 A.5.1.1 Outline of temperature and pressure ****************** ()--71 A.5.1.2 Thermal expansion ************************************ ()--74 1
A.5.1.3 Stress calculation *********************************** ()--75 A.5.1.4 Comparison of allowable stress *********************** ()--83 A.5.2 Water spray ********************************************* ()--85 A.5.3 Free drop *********************************************** ()--85 A.5.4 Stacking test ******************************************* ()--205 A.5.5 Penetration ********************************************* ()--211 A.5.6 Corner or edge drop ************************************* ()--213 A.5.7 Summary of results and evaluation *********************** ()--213 A.6 Accident test conditions *********************************** ()--214 A.6.1 Mechanical test - Drop test I (9m drop) ***************** ()--214 or mechanical test - Drop (dynamic pressure pickles)
A.6.1.1 Vertical drop **************************************** ()--220 A.6.1.2 Horizontal drop ************************************** ()--234 A.6.1.3 Corner drop ****************************************** ()--241 A.6.1.4 Inclined drop **************************************** ()--244 A.6.1.5 Summary of the results ******************************* ()--248 A.6.2 Mechanical test --- Drop (1m drop) ******************** ()--250 A.6.2.1 Summary of results *********************************** ()--256 A.6.3 Thermal test ******************************************** ()--257 A.6.3.1 Summary of temperatures and pressure ***************** ()--257 A.6.3.2 Thermal expansion ************************************ ()--257 A.6.3.3 Comparison of allowable stresses ********************* ()--258 A.6.4 Water immersion ***************************************** ()--260 A.6.5 Summary of result and evaluation ************************ ()--269 A.7 Reinforced immersion test ********************************** ()--271 A.8 Radioactive content **************************************** ()--271 A.9 Fissile package ******************************************** ()--272 A.9.1 Normal test conditions ********************************** ()--272 A.9.2 special test conditions for **************************** ()--274 fissionable transported articles 2
A.10 Appendix ************************************************** ()--279 B. Thermal analysis ******************************************** ()--1 B.1 General description **************************************** ()--1 B.2 Thermal properties of the materials ************************ ()--6 B.3 Specifications of components ******************************* ()--10 B.4 Normal test conditions ************************************* ()--11 B.4.1 Thermal analytical model ******************************** ()--11 B.4.1.1 Analytical model ************************************* ()--11 B.4.1.2 Test model ******************************************* ()--13 B.4.2 Maximum temperatures ************************************ ()--13 B.4.3 Minimum temperatures ************************************ ()--14 B.4.4 Maximum internal pressure ******************************* ()--14 B.4.5 Maximum thermal stress ********************************** ()--14 B.4.6 Summary of results and evaluation *********************** ()--15 B.5 Accident test conditions *********************************** ()--16 B.5.1 Thermal analytical model ******************************** ()--16 B.5.1.1 Analytical model ************************************* ()--16 B.5.1.2 Test model ******************************************* ()--20 B.5.2 Evaluation conditions for packages ********************** ()--21 B.5.3 Temperatures of packages ******************************** ()--21 B.5.4 Maximum internal pressure ******************************* ()--23 B.5.5 Maximum thermal stresses ******************************** ()--23 B.5.6 Summary of results and evaluation *********************** ()--24 B.6 Appendix *************************************************** ()--26 C. Containment analysis ***************************************** ()--1 C.1 General **************************************************** ()--1 C.2 Containment system ***************************************** ()--1 C.2.1 Containment system ************************************** ()--1 3
C.2.2 Penetration of containment system *********************** ()--4 C.2.3 Gasket and weldings of the containment system *********** ()--4 C.2.4 Lid ***************************************************** ()--5 C.3 Normal test conditions ************************************* ()--6 C.3.1 Leakage of radioactive materials ************************ ()--6 C.3.2 Pressurization of the containment system **************** ()--19 C.3.3 Coolant contamination *********************************** ()--19 C.3.4 Loss of coolant ***************************************** ()--19 C.4 Accident test conditions *********************************** ()--20 C.4.1 Fissile gas ********************************************* ()--20 C.4.2 Leakage of radioactive materials ************************ ()--21 C.5 Summary of the results and the evaluation ****************** ()--24 C.6 Appendix *************************************************** ()--25 D. Shield analysis ********************************************** ()--1 D.1 Outline **************************************************** ()--1 D.2 Radiation source specification ***************************** ()--1 D.2.1 Gamma radiation source ********************************** ()--2 D.2.2 Neutron source ****************************************** ()--11 D.3 Model specification **************************************** ()--14 D.3.1 Analysis model ****************************************** ()--14 D.3.2 Numeric density of atoms in each area of analysis model * ()--20 D.4 Shield evaluation ****************************************** ()--22 D.5 Summary of the results and evaluation ********************** ()--27 D.6 Appendix *************************************************** ()--29 E. Criticality analysis ***************************************** ()--1 E.1 General **************************************************** ()--1 E.2 Parts to be analyzed *************************************** ()--3 E.2.1 Content ************************************************* ()--3 4
E.2.2 Packaging *********************************************** ()--3 E.2.3 Neutron absorbing materials ***************************** ()--7 E.3 Model specification **************************************** ()--8 E.3.1 Calculation model *************************************** ()--8 E.3.2 Regional densities for each analyzed model region ******* ()--10 E.4 Evaluation for subcriticality ****************************** ()--28 E.4.1 Calculation conditions ********************************** ()--28 E.4.2 Water immersion into package **************************** ()--29 E.4.3 Calculation method ************************************** ()--29 E.4.4 Results ************************************************* ()--31 E.5 Benchmark test ********************************************* ()--34 E.6 Summary of results and evaluation ************************** ()--44 E.7 Appendix *************************************************** ()--45 F. Consideration of aging of nuclear fuel package *************** ()-F-1 F.1 Aging factors to consider ********************************** ()-F-1 F.2 Evaluation of the need to consider aging effect in safety analysis ***************************************** ()-F-2 F.3 Consideration of aging in safety analysis ****************** ()-F-9 G. Assessment of the compliance with the regulation and the notification ************* ()-G
() Handling methods and maintenance of nuclear fuel package A. Package handling methods ************************************* ()--1 A.1 Method of loading ****************************************** ()--1 A.2 Package inspection prior to shipment *********************** ()--2 A.3 Method of unloading **************************************** ()--2 A.4 Preparation of empty packaging ***************************** ()--2 5
B. Maintenance requirements ************************************* ()--1 B.1 Visual appearance inspection ******************************* ()--1 B.2 Pressure durability inspection ***************************** ()--1 B.3 Airtight leakage inspection ******************************** ()--1 B.4 Shielding inspection *************************************** ()--1 B.5 Subcriticality inspection ********************************** ()--1 B.6 Thermal inspection ***************************************** ()--1 B.7 Lifting inspection ***************************************** ()--1 B.8 Actuation check/inspection ********************************* ()--1 B.9 Maintenance of auxiliary systems *************************** ()--2 B.10 Maintenance of the valves, gaskets, etc. of sealing devices ()--2 B.11 Storage of the transport packaging ************************* ()--2 B.12 Retention of records *************************************** ()--2 B.13 Others ***************************************************** ()--2 (IV) Important Notice about a safe design and the safe transportation ********* (IV) 6
List of Figures Page Chapter I
()-Fig.A.1 Rough drawing of package *************************** ()--7
()-Fig.C.1 Rough drawing of package *************************** ()--2
()-Fig.C.2 Package under transport condition ****************** ()--3
()-Fig.C.3 Package under transport condition ****************** ()--4
()-Fig.C.4 Seal boundary of package *************************** ()--5
()-Fig.C.5 General drawing of package ************************* ()--9
()-Fig.C.6 Main body ****************************************** ()--10
()-Fig.C.7 Inner lid ****************************************** ()--11
()-Fig.C.8 Basket for box type fuel *************************** ()--12
()-Fig.C.9 Outer shell lid ************************************ ()--13
()-Fig.D.1 Metal spacer ************************************** ()--4
()-Fig.D.2 JRR-3 standard type fuel element ******************* ()--8 (uranium silicon aluminum dispersion alloy)
()-Fig.D.3 JRR-3 follower type fuel element ******************* ()--9 (uranium silicon aluminum dispersion alloy)
()-Fig.D.4 JRR-4B type fuel element *************************** ()--10
()-Fig.D.5 JRR-4L type fuel element *************************** ()--11
()-Fig.D.6 JRR-4 fuel element ********************************* ()--12 (uranium silicon aluminum dispersion type alloy)
()-Fig.D.7 JMTR standard fuel element ************************* ()--13
()-Fig.D.8 JMTR follower type fuel element ******************** ()--14
()-Fig.D.9 KUR standard and half-loaded fuel element ********** ()--15 (uranium silicon aluminum dispersion type alloy)
()-Fig.D.10 KUR special fuel element *************************** ()--16 (uranium silicon aluminum dispersion type alloy)
()-Fig.D.11 JMTRC standard fuel element *********************** ()--17 (A type, B type, C type)
()-Fig.D.12 JMTRC standard fuel element (pin fix type) ******** ()--18 (C type)
()-Fig.D.13 JMTRC special fuel element (special A type) ******** ()--19
()-Fig.D.14 JMTRC special fuel element (special B type) ******** ()--20
()-Fig.D.15 JMTRC special fuel element ************************* ()--21 7
(special C type, special D type)
()-Fig.D.16 JMTRC fuel follower (HF type) ********************** ()--22
()-Fig.D.17 JMTRC standard fuel element (MA, MB, MC type) ****** ()--23
()-Fig.D.18 JMTRC special fuel element ************************* ()--24 (special MB type, special MC type)
()-Fig.D.19 JMTRC fuel follower (MF type) ********************** ()--25
()-Fig.D.20 KUCA Coupon type fuel ****************************** ()--26
()-Fig.D.21 KUCA flat type fuel ******************************** ()--27 8
Chapter
()-Fig.A.1 Position of center of gravity ********************** ()--33
()-Fig.A.2 Variations in mechanical properties of ************* ()--37 SUS304 according to changes in temperature (1/5)
()-Fig.A.2 Variations in mechanical properties of ************* ()--38 SUS304 according to changes in temperature (2/5)
()-Fig.A.2 Variations in mechanical properties of ************* ()--39 SUS304 according to changes in temperature (3/5)
()-Fig.A.2 Variations in mechanical properties of ************* ()--40 SUS304 according to changes in temperature (4/5)
()-Fig.A.2 Variations in mechanical properties of ************* ()--41 SUS304 according to changes in temperature (5/5)
()-Fig.A.3 Variations in mechanical properties of ************* ()--42 SUS630 according to changes in temperature (bolt material)(1/4)
()-Fig.A.3 Variations in mechanical properties of ************* ()--43 SUS630 according to changes in temperature (bolt material)(2/4)
()-Fig.A.3 Variations in mechanical properties of ************* ()--44 SUS630 according to changes in temperature (bolt material)(3/4)
()-Fig.A.3 Variations in mechanical properties of ************* ()--45 SUS630 according to changes in temperature (bolt material)(4/4)
()-Fig.A.4 Variations in mechanical properties of ************* ()--46 SUS630 according to changes in temperature(1/1)
()-Fig.A.5 Variations in mechanical properties of ************* ()--47 AG3NE according to changes in temperature (1/1)
()-Fig.A.6 Design fatigue curve (austenitic type stainless **** ()--48 steel and high nickel alloy)
()-Fig.A.7 Design fatigue curve ******************************* ()--48 (high tensile strength bolt)
()-Fig.A.8 Stress-strain curve of shock absorber ************** ()--49
()-Fig.A.9 Analytical model for eye-plate ********************* ()--53
()-Fig.A.10 Analytical model of welded part on eye-plate ******* ()--56
()-Fig.A.11 Acceleration during transportation ***************** ()--58
()-Fig.A.12 Analytical model for eye-plate ********************* ()--60
()-Fig.A.13 Analytical model for welded part of eye-plate ****** ()--63
()-Fig.A.14 Vibration analytical model of packaging ************ ()--68
()-Fig.A.15 Analytical model of thermal expansion ************** ()--73 9
()-Fig.A.16 Stress evaluation position under ******************* ()--75 normal test conditions
()-Fig.A.17 Stress analysis model of inner shell *************** ()--76 center portion
()-Fig.A.18 Stress analysis model of inner shell bottom plate ** ()--77
()-Fig.A.19 Stress analysis model of inner lid center portion ** ()--78
()-Fig.A.20 Analytical model of inner lid O-ring displacement ** ()--79
()-Fig.A.21 Stress analysis model of bolt of the inner lid ***** ()--80 (initial clamping stress)
()-Fig.A.22 Stress analysis model of bolt of inner lid ********* ()--81 (stress due to internal pressure)
()-Fig.A.23 Stress analysis model of bolt of inner lid ********* ()--82 (stress due to thermal expansion)
()-Fig.A.24 Acceleration evaluation position of steel plate **** ()--88 for horizontal drop
()-Fig.A.25 Acceleration analysis model of outer shell plate *** ()--89 for horizontal drop
()-Fig.A.26 Cross section of outer shell lid flange ************ ()--92
()-Fig.A.27 Acceleration analysis model of outer shell head **** ()--95 plate for horizontal drop
()-Fig.A.28 Cross section of partition plate ******************* ()--97
()-Fig.A.29 Deformation analysis model of eye plate ************ ()--99
()-Fig.A.30 Analytical model of eye-plate fixing-plate ********* ()--100
()-Fig.A.31 Analytical model of flange of outer shell ********** ()--102
()-Fig.A.32 Analytical model of eye-plate fixing lug *********** ()--104
()-Fig.A.33 Acceleration analysis model of steel plate ******** ()--106 for vertical drop
()-Fig.A.34 Acceleration analysis model of steel plate ********* ()--108 for corner drop
()-Fig.A.35 Stress evaluation position for 1.2m **************** ()--111 horizontal drop (main body of inner shell)
()-Fig.A.36 Analytical model of interference to inner shell **** ()--112 due to shock absorber deformation for 1.2m horizontal drop
()-Fig.A.37 Stress analysis model of inner shell for *********** ()--113 1.2m horizontal drop
()-Fig.A.38 Stress analysis model of inner shell *************** ()--114 bottom plate for 1.2m horizontal drop
()-Fig.A.39 Stress analysis model of inner she11 *************** ()--115 upper part for 1.2m horizontal drop 10
()-Fig.A.40 Stress analysis model for inner lid **************** ()--117 clamping bolt for 1.2m horizontal drop
()-Fig.A.41 Analytical model of section ************************ ()--118 modulus of rectangular fuel basket
()-Fig.A.42 Evaluation of fuel elements for l.2m *************** ()--122 horizontal drop
()-Fig.A.43 Analytical model of rectangular fuel elements for ** ()--123 l.2m horizontal drop perpendicular to fuel plate
()-Fig.A.44 Analytical model of rectangular fuel element for *** ()--124 1.2m horizontal drop parallel to fuel plate
()-Fig.A.45 Analytical model of holder ************************* ()--129
()-Fig.A.46 Analytical model of fuel plate for ***************** ()--130 1.2m horizontal drop parallel to fuel plate
()-Fig.A.47 Analytical model of coupon fuel for **************** ()--131 1.2m horizontal drop
()-Fig.A.48 Analytical model of flat fuel plate for 1.2 m ****** ()--132 horizontal drop in the plane direction of the fuel plate
()-Fig.A.49 Analytical model of flat fuel plate for 1.2 m ****** ()--133 horizontal drop in the direction parallel to the fuel plate
()-Fig.A.50 Stress evaluation position for 1.2m lower ********** ()--141 side vertical drop (main body of packaging)
()-Fig.A.51 Analytical model of interference to inner shell **** ()--142 due to shock absorber deformation for 1.2m lower side vertical drop
()-Fig.A.52 Stress analysis model of inner shell for *********** ()--143 1.2m lower side vertical drop
()-Fig.A.53 Stress analysis model of inner shell bottom ******** ()--144 plate for 1.2m lower side vertical drop
()-Fig.A.54 Stress analysis model of inner lid for ************* ()--146 1.2m lower side vertical drop
()-Fig.A.55 Stress analysis model of rectangular fuel ********** ()--148 element for 1.2m lower side vertical drop
()-Fig.A.56 Analytical model of 1.2m lower portion ************* ()--150 vertical drop of lowly irradiated fuel element
()-Fig.A.57 Analytical model of 1.2m lower portion vertical **** ()--152 drop of lowly irradiated fuel element
()-Fig.A.58 Analytical model of hold down part ***************** ()--153
()-Fig.A.59 Analytical model of 1.2m vertical drop: *********** ()--155 coupon fuel 11
()-Fig.A.60 Analytical model of 1.2m vertical drop: coupon fuel ()--156 flat fuel
()-Fig.A.61 Stress evaluation position for 1.2m lid side ******* ()--164 vertical drop (main body of a packaging)
()-Fig.A.62 Analytical model of interference inner ************* ()--165 shell due to shock absorber deformation for 1.2m lid side vertical drop
()-Fig.A.63 Stress analysis model of inner shell for *********** ()--166 1.2m lid side vertical drop
()-Fig.A.64 Stress analysis model of inner shell *************** ()--167 bottom plate for 1.2m lid side vertical drop
()-Fig.A.65 Stress analysis model of inner lid for ************* ()--169 1.2m lid side vertical drop
()-Fig.A.66 Stress analysis model of rectangular fuel ********** ()--175 element for l.2m lid side vertical drop
()-Fig.A.67 Analytical model of 1.2m upper portion ************ ()--177 vertical drop of lowly irradiated fuel element
()-Fig.A.68 Analytical model for 1.2m upper portion vertical *** ()--179 drop of lowly irradiated fuel element
()-Fig.A.69 Analytical model of hold down part ***************** ()--180
()-Fig.A.70 Analytical model of interference to inner shell **** ()--191 due to shock absorber deformation for 1.2m corner drop
()-Fig.A.71 Analytical model of stress on inner lid ************ ()--193 clamping bolts for lid side corner drop
()-Fig.A.72 Analytical model of interference with inner shell ** ()--197 due to shock absorber deformation for 1.2m lower side inclined drop
()-Fig.A.73 Relationship between acceleration and drop angle *** ()--198 for 1.2m lower side inclined drop
()-Fig.A.74 Analytical model of interference with inner shell ** ()--199 due to shock absorber deformation for 1.2m upper side inclined drop
()-Fig.A.75 Relationship between acceleration and drop angle *** ()--200 for 1.2m upper side inclined drop
()-Fig.A.76 Stress evaluation position for compressive load **** ()--202
()-Fig.A.77 Analytical model of inner lid under **************** ()--202 compressive load
()-Fig.A.78 Analytical model of inner shell under ************** ()--204 compressive load
()-Fig.A.79 Penetration model ********************************** ()--207
()-Fig.A.80 Shearing model ************************************* ()--208 12
()-Fig.A.81 Analytical model of interference to inner shell **** ()--216 due to shock absorber deformation for 9m lower side vertical drop
()-Fig.A.82 Analytical model of interference to inner shell **** ()--223 due to shock absorber deformation for 9m upper side vertical drop
()-Fig.A.83 Analytical model of interference to inner shell **** ()--230 due to shock absorber deformation for 9m horizontal drop
()-Fig.A.84 Analytical model of interference to inner shell **** ()--237 due to shock absorber deformation for 9m corner drop
()-Fig.A.85 Analytical model of interference to inner shell **** ()--240 due to shock absorber deformation for 9m lower side inclined drop
()-Fig.A.86 Relationship between acceleration and drop angle *** ()--241 for 9m lower side inclined drop
()-Fig.A.87 Analytical model of interference to inner shell **** ()--242 due to shock absorber deformation for 9m upper side inclined drop
()-Fig.A.88 Relationship between acceleration and drop angle *** ()--243 for 9m upper side inclined drop
()-Fig.A.89 Analytical model for drop test ****************** ()--246
()-Fig.A.90 Analytical model for penetration strength ********** ()--248 under conditions of drop test
()-Fig.A.91 Stress evaluation position of inner shell ********** ()--256 for 15m immersion test
()-Fig.A.92 Analytical model of allowable buckling ************* ()--257 pressure for frame of inner shell
()-Fig.A.93 Curve representing buckling behavior factor ******** ()--258 of inner shell under external pressure
()-Fig.A.94 Stress analysis model of center of inner shell ***** ()--259
()-Fig.A.95 Stress analysis model of bottom plate ************** ()--260 of inner shell
()-Fia.A.96 Stress analysis model of center of inner lid ******* ()--261
()-Fig.A.97 Displacement analysis model of O-rings of ********** ()--262 inner lid under external pressure
()-Fig.A.98 Normal test conditions ***************************** ()--268
()-Fig.A.99 Accident test condition **************************** ()--270
()-Fig.A.100 Drop attitude and test order *********************** ()--272
()-Fig.A.101 Analytical model of shock absorber ***************** ()--276 13
()-Fig.A.102 Analytical model by uniaxial displacement method *** ()--277
()-Fig.A.103 Compressive stress/strain relationship of materials ()--278
()-Fig.A.104 Proportion of shock absorber *********************** ()--281
()-Fig.A.105 Analytical model of inner lid for 1.2m ************* ()--283 lid side vertical drop
()-Fig.A.106 Stress/strain characteristics curves for *********** ()--288 shock absorber at low temperatures
()-Fig.A.107 Stress/strain curves for hard polyurethane foam **** ()--289
()-Fig.A.108 Low temperature strength of SUS 304 **************** ()--290
()-Fig.A.109 Low temperature impact value of SUS 304 ************ ()--291
()-Fig.A.110 Low temperature impact value of SUS 630H1150 ****** ()--292
()-Fig.A.111 Analytical model for initial clamping force ******** ()--293 of inner lid clamping bolts
()-Fig.A.112 Triangle diagram for inner lid clamping bolt ******* ()--298
()-Fig.B.1 Component of packaging ***************************** ()--3
()-Fig.B.2 Concept of thermal transmission ******************** ()--4
()-Fig.B.3 Two dimensional axis symmetrical model ************* ()--17
()-Fig.B.4 Temperature time history under accident ************ ()--22 test conditions
()-Fig.B.5 TRUMP flowchart (1/3)***************************** ()--32
()-Fig.B.5 TRUMP flowchart (2/3)***************************** ()--33
()-Fig.B.5 TRUMP flowchart (3/3)***************************** ()--34
()-Fig.B.6 Fuel basket model ********************************** ()--35
()-Fig.B.7 Comparison of prototype packaging test results ***** ()--43 with analysis results
()-Fig.C.1 Containment boundary of packaging ****************** ()--3
()-Fig.D.1 Neutron fission energy spectrum ******************** ()--12
()-Fig.D.2 Gamma radiation shield calculation model *********** ()--16
()-Fig.D.3 Relationship between packaging surface angles ****** ()--17 flux and calculation point of packaging surface 14
()-Fig.D.4 Neutron shield calculation model ******************* ()--19
()-Fig.D.5 Mesh distribution drawing ************************** ()--31
()-Fig.E.1 Calculation model of arrayed packages for ********** ()--11 criticality with 10 box type fuel elements (except KUR)
()-Fig.E.2 Calculation model of arrayed packages for ********** ()--12 criticality with 10 box type fuel elements (KUR and KUCA fuel)
()-Fig.E.3 Calculation model of package for criticality ******* ()--13 with 10 box type fuel elements
()-Fig.E.4 Calculation model of package for criticality ******* ()--14 with HEU and MEU
()-Fig.E.5 Criticality calulation model of JRR-3 ************** ()--15 standard fuel element
()-Fig.E.6 Criticality calculation model of JRR-4B type ******* ()--16 fuel element
()-Fig.E.7 Criticality calculation model of JRR-4L type ******* ()--17 fuel element
()-Fig.E.8 Criticality calculation model JRR-4 type *********** ()--18 fuel element
()-Fig.E.9 Criticality calculation model of JMTR standard ******* ()--19 type fuel element
()-Fig.E.10 Criticality calculation model of JMTRC standard *** ()--20 type fuel element (HEU)
()-Fig.E.11 Criticality calculation model of JMTRC standard***** ()--21 type fuel element (MEU)
()-Fig.E.12 Criticality calculation model of KUR standard******* ()--22 type fuel element
()-Fig.E.13 Criticality calculation model of KUCA coupon******** ()--23 type fuel
()-Fig.E.14 Criticality calculation model of KUCA flat ********** ()--24 type fuel element
()-Fig.E.15 Schematic flow of criticality analysis ************* ()--30
()-Fig.E.14 Relationship between effective multiplication ****** ()--32 factor (keff+/-3) and water density (contained ten JRR-3 standard type fuel elements (uranium silicon aluminum dispersion type alloy))
()-Fig.E.16 Configuration of TCA criticality experiments ******* ()--38
()-Fig.E.17 SPERT-D fuel *************************************** ()--39 15
()-Fig.E.18 SPERT-D fuel (continued) *************************** ()--40
()-Fig.E.19 Core arrangement *********************************** ()--41
()-Fig.E.20 Fuel element *************************************** ()--42
()-Fig.E.21 Core arrangement *********************************** ()--43
()-Fig.E.22 Relationship between effective multiplication ****** ()--48 factor (keff+/-3) and water density type fuel element (contained ten JRR-3 standard type fuel elements (uranium silicon Aluminum dispersion type alloy))
Chapter
()-Fig.B.1 Quality assurance organization for design of the transport packaging *****************()-8 16
List of Tables Chapter
()-Table A.1 Specification of fuel enclosed in package ******** ()--3
()-Table C.1 Material of packaging **************************** ()--15
()-Table C.2 Dimension of packaging *************************** ()--16
()-Table C.3 Weight of packaging ****************************** ()--17
()-Table D.1 Specification of fuel element ******************** ()--5 (fresh fuel element)
()-Table D.2 Specification of fuel element ******************** ()--6 (lowly irradiated fuel element)
()-Table D.3 Specification of fuel element ******************** ()--7 (fresh fuel for KUCA)
Chapter
()-Table A.1 Design standard for structural analysis ********** ()--4
()-Table A.2 Design load, combination of load (1/2) *********** ()--5
()-Table A.2 Design load, combination of load (2/2) *********** ()--6
()-Table A.3 Load condition (1/2) ***************************** ()--7
()-Table A.3 Load condition (2/2) ***************************** ()--8
()-Table A.4 Design conditions, analytical methods ************ ()--9 of structural analysis (1/24)
()-Table A.4 Design conditions, analytical methods ************ ()--10 of structural analysis (2/24)
()-Table A.4 Design conditions, analytical methods ************ ()--11 of structural analysis (3/24)
()-Table A.4 Design conditions, analytical methods ************ ()--12 of structural analysis (4/24)
()-Table A.4 Design conditions, analytical methods ************ ()--13 of structural analysis (5/24)
()-Table A.4 Design conditions, analytical methods ************ ()--14 of structural analysis (6/24)
()-Table A.4 Design conditions, analytical methods ************ ()--15 of structural analysis (7/24)
()-Table A.4 Design conditions, analytical methods ************ ()--16 of structural analysis (8/24) 17
()-Table A.4 Design conditions, analytical methods ************ ()--17 of structural analysis (9/24)
()-Table A.4 Design conditions, analytical methods ************ ()--18 of structural analysis (10/24)
()-Table A.4 Design conditions, analytical methods ************ ()--19 of structural analysis (11/24)
()-Table A.4 Design conditions, analytical methods ************ ()--20 of structural analysis (12/24)
()-Table A.4 Design conditions, analytical methods ************ (II)--21 of structural analysis (13/24)
()-Table A.4 Design conditions, analytical methods ************ ()--22 of structural analysis (14/24)
()-Table A.4 Design conditions, analytical methods ************ ()--23 of structural analysis (15/24)
()-Table A.4 Design conditions, analytical methods ************ ()--24 of structural analysis (16/24)
()-Table A.4 Design conditions, analytical methods ************ ()--25 of structural analysis (17/24)
()-Table A.4 Design conditions, analytical methods ************ ()--26 of Structural analysis (18/24)
()-Table A.4 Design conditions, analytical methods ************ ()--27 of structural analysis (19/24)
()-Table A.4 Design conditions, analytical methods ************ ()--28 of structural analysis (20/24)
()-Table A.4 Design conditions, analytical methods ************ ()--29 of structural analysis (21/24)
()-Table A.4 Design conditions, analytical methods ************ ()--30 of structural analysis (22/24)
()-Table A.4 Design conditions, analytical methods ************ ()--31 of structural analysis (23/24)
()-Table A.4 Design conditions, analytical methods ************ ()--32 of structural analysis (24/24)
()-Table A.5 Mechanical properties of materials *************** ()--35
()-Table A.6 Mechanical properties of materials to be used **** ()--36 as design standards
()-Table A.7 List of different materials contacted ************ ()--50
()-Table A.8 Minimum temperatures of parts of package ********* ()--51
()-Table A.9 Summary of analyses under routine transport ****** ()--65 18
()-Table A.10 Stresses evaluation under changed pressure ******* ()--67
()-Table A.11 Design temperature under normal test conditions ** ()--71
()-Table A.12 Design pressure under normal test conditions ***** ()--72
()-Table A.13 Stress evaluation under normal test conditions *** ()--83 (thermal test)
()-Table A.14 Deformation and acceleration of shock ************ ()--87 absorber under normal test conditions
()-Table A.15 Design acceleration under normal test conditions * ()--110
()-Table A.16 Stress evaluation for 1.2m horizontal drop (1/6) ** ()--135
()-Table A.16 Stress evaluation for 1.2m horizontal drop (2/6) ** ()--136
()-Table A.16 Stress evaluation for 1.2m horizontal drop (3/6) ** ()--137
()-Table A.16 Stress evaluation for 1.2m horizontal drop (4/6) ** ()--138
()-Table A.16 Stress evaluation for 1.2m horizontal drop (5/6) ** ()--139
()-Table A.16 Stress evaluation for 1.2m horizontal drop (6/6) ** ()--140
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--158 vertical drop(1/6)
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--159 vertical drop(2/6)
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--160 vertical drop(3/6)
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--161 vertical drop(4/6)
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--162 vertical drop(5/6)
()-Table A.17 Stress evaluation for 1.2m bottom side *********** ()--163 vertical drop(6/6)
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--185 vertical drop (1/6)
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--186 vertical drop (2/6)
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--187 vertical drop (3/6)
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--188 vertical drop (4/6)
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--189 vertical drop (5/6) 19
()-Table A.18 Stress evaluation for 1.2m lid side ************** ()--190 vertical drop (6/6)
()-Table A.19 Design acceleration for corner drops ************* ()--192
()-Table A.20 Stress evaluation for 1.2m lid side ************** ()--196 corner drop
()-Table A.21 Relationship between drop angle and acceleration * ()--198
()-Table A.22 Relationship between drop angle and acceleration * ()--199
()-Table A.23 Stress evaluation for stacking test ************** ()--206
()-Table A.24 Deformation and acceleration of shock absorber *** ()--214 under accident test conditions
()-Table A.25 Design acceleration under accident *************** ()--215 test conditions
()-Table A.26 Stress evaluation for 9m lower side ************** ()--217 vertical drop (1/6)
()-Table A.26 Stress evaluation for 9m lower side ************** ()--218 vertical drop (2/6)
()-Table A.26 Stress evaluation for 9m lower side ************** ()--219 vertical drop (3/6)
()-Table A.26 Stress evaluation for 9m lower side ************** ()--220 vertical drop (4/6)
()-Table A.26 Stress evaluation for 9m lower side ************** ()--221 vertical drop (5/6)
()-Table A.26 Stress evaluation for 9m lower side ************** ()--222 vertical drop (6/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--224 vertical drop (1/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--225 vertical drop (2/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--226 vertical drop (3/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--227 vertical drop (4/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--228 vertical drop (5/6)
()-Table A.27 Stress evaluation for 9m upper side ************** ()--229 vertical drop (6/6)
()-Table A.28 Stress evaluation for 9m horizontal drop (1/6) *** ()--231
()-Table A.28 Stress evaluation for 9m horizontal drop (2/6) *** ()--232 20
()-Table A.28 Stress evaluation for 9m horizontal drop (3/6) *** ()--233
()-Table A.28 Stress evaluation for 9m horizontal drop (4/6) *** ()--234
()-Table A.28 Stress evaluation for 9m horizontal drop (5/6) *** ()--235
()-Table A.28 Stress evaluation for 9m horizontal drop (6/6) *** ()--236
()-Table A.29 Design acceleration for corner drop ************** ()--238
()-Table A.30 Stress evaluation for 9m upper corner drop ******* ()--239
()-Table A.31 Relationship between drop angle and acceleration * ()--241
()-Table A.32 Relationship between drop angle ****************** ()--243 and acceleration for drop test
()-Table A.33 Relationship between drop angle ****************** ()--244 and acceleration for drop test
()-Table A.34 Evaluation of penetration for drop test ******* ()--252
()-Table A.35 Design temperatures used for ********************* ()--253 accident test condition
()-Table A.36 Design pressure of package under accident ******** ()--253 condition
()-Table A.37 Stress analysis and evaluation under accident **** ()--255 test conditions (thermal test)
()-Table A.38 Stresses evaluated for 15m water immersion test ** ()--264
()-Table A.39 Damages of the fissile package under the normal ** ()--269 test conditions
()-Table A.40 Compliance with requirements for fissile package ()--269 under normal test conditions
()-Table A.41 Deformations and design accelerations of shock *** ()--273 absorber under accident test conditions (combined evaluation)
()-Table A.42 Damage of the fissile package under special test * ()--274 conditions
()-Table A.43 Comparisons of analytical values ***************** ()--281 by CASH- and experimental values
()-Table A.44 Comparison of analytical and experimental ******** ()--282 results
()-Table A.45 Analysis results of displacement of ************** ()--287 inner O-rings of inner lid
()-Table B.1 Conditions of thermal analyses ******************* ()--5
()-Table B.2 Methods of thermal analyses ********************** ()--6 21
()-Table B.3 Thermal properties of stainless steel ************ ()--7
()-Table B.4 Thermal properties of air ************************ ()--7
()-Table B.5 Thermal properties of shock absorber (balsa) ***** ()--8
()-Table B.6 Thermal properties of heat insulator ************* ()--9 (hard polyurethane foam)
()-Table B.7 Specifications of silicone rubber O-ring ********* ()--10
()-Table B.8 Specifications of fusible plug ******************* ()--10
()-Table B.9 Thermal conditions under normal test conditions ** ()--12
()-Table B.10 Maximum temperatures of each part of package ***** ()--13
()-Table B.11 Thermal conditions under accident test conditions * ()--19
()-Table B.12 Maximum temperatures of package under accident *** ()--21 test conditions
()-Table B.13 Maximum pressure in packaging under accident ***** ()--25 test conditions
()-Table B.14 Convection heat transfer coefficient between ***** ()--37 package surface and ambient environment
()-Table B.15 Radiation factor and radiation morphological ***** ()--37 coefficient
()-Table B.16 Calculation result for packaging internal ******** ()--40 pressure
()-Table B.17 Design pressures for specific test conditions **** ()--41
()-Table B.18 Comparison of prototype packaging test results *** ()--42 with analysis results
)-Table C.1 Design pressure and design temperature of ********* ()--2 containment system
()-Table C.2 The dimensions and material of the gasket ******** ()--5
()-Table C.3 Inner shell clamping bolt ************************ ()--5
()-Table C.4 Maximum permissible leakage rate of the air ****** ()--7
()-Table C.5 The maximum radius of leak hole on leakage rate ** ()--10 test
()-Table C.6 The maximum gas leakage rate under normal test *** ()--11 conditions 234 236
()-Table C.7 Weight proportions of U and U used for ******* ()--13 caluculations
()-Table C.8 Surface contamination level per fuel element **** ()--14 22
()-Table C.9 Leakage rate of radioactive substances under ***** ()--15 normal test condition
()-Table C.10 Nuclide of JMTRC fuel surface water and ********** ()--16 radioactive concentration
()-Table C.11 Surface activity per one fuel element of lowly ** ()--17 irradiated fuel element
()-Table C.12 Leak rate of the radioactivity under normal ****** ()--18 test condition
()-Table C.13 The maximum gas leakage rate under the accident * ()--21 test conditions
()-Table C.14 Leakage rate of radioactive substances under *** ()--23 normal test conditions
()-Table C.15 Leakage rate of radioactive substances under **** ()--23 accident test condition
()-Table D.1 Gamma radiation emission rate of uranium ********* ()--3 isotope
()-Table D.2 Gamma radiation source intensity for one fuel **** ()--3 element
()-Table D.3 Specific activity used for calculation *********** ()--4 234 236
()-Table D.4 U and U weight rate used for calculation ****** ()--4
()-Table D.5 Radioactive nuclide weight per one element used ** ()--4 in calculation
()-Table D.6 Gamma radiation emission rate of uranium isotope * ()--7
()-Table D.7 Gamma radiation source intensity per ************* ()--7 one mixed fuel element (actinoids)
()-Table D.8 Specific activity used for calculation *********** ()--8 234 236
()-Table D.9 U and U weight rate used for calculation ****** ()--8
()-Table D.10 Radioactive nuclide weight per one element ******* ()--8 used in calculation
()-Table D.11 Radioactivity rate of the fission products ******* ()--10 obtained by ORIGEN
()-Table D.12 Uranium isotope spontaneous fission speed ******** ()--11
()-Table D.13 Emission rate of spontaneous fission of ********** ()--13 uranium isotope
()-Table D.14 Material and density ***************************** ()--20 23
()-Table D.15 Volumetric rate of shield material for each ****** ()--20 area used in shield calculation
()-Table D.16 Atom density for each material ******************* ()--21
()-Table D.17 Gamma radiation energy group structure and ******* ()--23 dose-equivalent rate calculation factor
()-Table D.18 Dose-equivalent rate by gamma radiation ********** ()--24 (fresh fuel elements loading)
()-Table D.19 Dose-equivalent rate by gamma radiation ********** ()--24 (lowly irradiated fuel elements loading)
()-Table D.20 Neutron dose-equivalent rate ********************* ()--25
()-Table D.21 Dose-equivalent rate of neutron irradiation ****** ()--26 (lowly irradiated fuel elements loading)
()-Table D.22 Package dose-equivalent rate ********************* ()--27 (fresh fuel element loading)
()-Table D.23 Package dose-equivalent rate ********************* ()--28 (lowly irradiated fuel elements loading)
()-Table E.1 Specifications of fuel element ******************* ()--4
()-Table E.2 Specification of fuel plate (1/2) **************** ()--5
()-Table E.2 Specification of fuel plate (2/2) **************** ()--6
()-Table E.3 Distance from the surface of the inner shell ***** ()--7 to the surface of the packaging
()-Table E.4 Requirements defined in the regulation *********** ()--25 And analysis condition
()-Table E.5 Atom density of regions used in ****************** ()--26 criticality calculation (atoms/barncm)
()-Table E.6 Atom density of fuel element used in ************* ()--27 criticality calculation (atoms/barncm)
()-Table E.7 Fuel elements to be analyzed ********************* ()--28
()-Table E.8 Results of criticality analysis when immersed **** ()--33
()-Table E.9 Analysis result of benchmark criticality test **** ()--37
()-Table E.10 Effective multiplication factor for various ****** ()--47 water density [contained ten JRR-3 standard type fuel elements (uranium silicon aluminum dispersion type alloy) and (300 KUCA flat plates in a package)]
24
()-Table F.1 Assessment of the compliance with the technical standards stipulated in the regulation and the notification ****************************** ()--2 Chapter Chapter
()-Table A.1 Procedures for pre-shipment inspection of the package *********************************** ()--3 25
(I) Description of nuclear fuel package
Purpose and conditions
(I) Description of nuclear fuel package (I)-A. Purpose and conditions This packaging is intended for carrying fresh fuel elements to be charged into Kyoto University Research Reactor (KUR) and Kyoto University Critical Assembly (KUCA) installed at the Institute for Integrated Radiation and Nuclear Science, Kyoto University, from fabrication plants, domestic and overseas, to KUR and KUCA. Moreover, this packaging is intended for carrying experimental nuclear materials from the Institute for Integrated Radiation and Nuclear Science, Kyoto University.
In addition, this packaging is intended for carrying fresh fuel elements to be charged into JRR-3 installed at the Tokai Research Institute of the Japan Atomic Energy Agency (JAEA) and into JMTR and JMTRC installed at the Oarai Research Institute, from fabrication plants, domestic and overseas, to JRR-3 etc.
Moreover, this is also intended to transport JRR-4 installed at the Nuclear Science Research Institute and the JMTRs new fuel elements installed at the Oarai Research and Development Center, as well as fuels low-irradiated in the JMTRC of the Oarai Research and Development Center to overseas counties or regions.
The conceptual drawing of this packaging is shown in ()-Fig.A.1.
(1) Name of packaging JRF-90Y-950K (2) Type BU type fissile package (3) Allowable number of packages Unlimited (4) Allowable arrangement of packages Not specified (5) Transport index 1.9 or less (6) Criticality safety index 0 (7) Weight of package 950kg or less (8) Size of packaging (a) Diameter approx. 840mm (b) Height approx. 1800mm (9) Maximum weight of packaging approx. 860kg (Rectangular fuel element loaded) 1
(10) Main materials for packaging (a) Main body : Stainless steel, Balsa wood, Hard polyurethane foam (b) Outer lid : Stainless steel, Balsa wood, Hard polyurethane foam (c) Inner lid : Stainless steel, Silicone rubber (d) Fuel basket : Stainless steel, Silicone rubber (11) Nuclear fuels contained in packaging The packaging may contain low-enriched uranium (called LEU fuel here in after), medium-enriched uranium and high-enriched uranium (referred to HEU fuel hereafter) fuel elements for research reactor. These fuels are categorized as, based on their usage purpose, the standard fuel element, the half-loaded fuel element, the special fuel element and the fuel follower. In addition, coupon type and flat type fuels using low-enriched uranium may be contained as fuels for critical assembly. Moreover, the packaging may contain high-enriched uranium spectrum converter for experimental nuclear material (called Spectrum converter here in after).
(a) Non-irradiated fresh fuels for research reactor : 10 or less The fresh fuels having the equal nominal enrichment only are contained.
(b) Lowly irradiated fuels : 10 or less The lowly irradiated fuels, HEU and MEU, are contained together.
(c) Non-irradiated fresh fuels for KUCA Coupon type fuels : 1200 or less Flat type fuels : 300 or less The KUCA fuels having same fuel type only are contained.
(d) Lowly irradiated high enriched uranium spectrum converter: 1 (12) Specifications for nuclear fuels contained in packaging The specification for fuel is shown in ()-Table A.1.
(13) Form of shipment (a) Transport method Sea transport is done by seagoing vessels and transport over land is done 2
by carrier. Each is exclusively loaded.
(b) Loading method The packaging is tightly fastened with specially designed tools.
(14) Expiration years of use (a) Expiration years of use: 40 years (b) Number of transports per year: 3 or less (c) Number of days required for one transport: 100 or less 3
(I)-Table A.1 Specification of nuclear material contained in shipping container (1/5) (KUR Fresh Fuel Element)
Reactor KUR (Kyoto University Research reactor)
KUR KUR KUR Fuel Element Standard Fuel Element Special Fuel Element Half-loaded Fuel Element Number of Fuel Elements (element/package) 10 or less Fuel Type LEU fuel Materials of Nuclear Fuel Uranium-silicon -aluminum dispersion alloy 235 U weight (g or less/package) 2,180 1,090 1,090 U weight (g or less/package) 11,150 5,580 5,580 Weight 235 U weight (g or less/element) 218 109 109 U weight (g or less/element) 1,115 558 558 Enrichment (wt% or less) 19.95 4
Total (GBq or less/package) 29.8 234 U 28.6 Activity of 235 Principal Radionuclide U 0.38 Contents 236 (GBq or less/package) U 0.59 238 U 0.24 Physical State Solid Burn-up (% or less) 0 (Non-irradiated fresh Fuel)
Total Heat Generation Rate 0 (Non-irradiated fresh Fuel)
(W or less/package)
Cooling Time (days) 0 (Non-irradiated fresh Fuel)
-Loading a transport package with different types of nuclear fuel material is allowed for each reactor only when all the fuel elements contained are the same type having the same enrichment level.For the nuclear fuel material from JMTRC, however, mixed loading of fuel elements of different types and different enrichment levels is allowed.
- The values of weight and heat generation are calculated proportionally from the maximum weight and heat generation for each type of fuel element according to the number of assemblies contained.
- The absorbed dose rate to air at a position 1 m away from the surface of the package is 1 Gy/h or less.
(I)-Table A.1 Specification of nuclear material contained in shipping container (2/5) (Fresh Fuel Element)
Reactor JRR-3 JRR-4 JMTR JRR-3 JRR-3 standard follower JRR-4B type JRR-4L type fuel JRR-4 type fuel JMTR fuel Fuel Element JMTR standard fuel element fuel type fuel fuel element element element followers element element Number of Fuel Elements 10 or less (element/package)
Fuel Type LEU fuel HEU fuel LEU fuel MEU fuel LEU fuel Uranium-silicon Uranium Uranium-silicon Uranium-silicon Uranium-aluminum Uranium-aluminum Materials of Nuclear Fuel -aluminum dispersion -aluminum -aluminum -aluminum dispersion alloy dispersion alloy alloy alloy dispersion alloy dispersion alloy 235 U weight 4,850 3,100 1,700 2,300 2,100 3,200 4,250 2,800 (g or less/package)
U weight 24,810 15,860 1,830 11,770 10,750 7,280 21,740 14,330 (g or less/package)
Weight 235 U weight 485 310 170 230 210 320 425 280 (g or less/element) 5 U weight 2,481 1,586 183 1,177 1,075 728 2,174 1,433 (g or less/element)
Enrichment 19.95 93.3 19.95 46.0 19.95 (wt% or less)
Total 29.8 (GBq or ess/package)
Activity 234 Principal U: 28.6 of 235 Contents Radionuclide U: 0.38 236 (GBq or U: 0.59 238 less/package) U: 0.24 Physical State Solid Burn-up 0 (Fresh Fuel)
(% or less)
Total Heat Generation Rate 0 (Fresh Fuel)
(W or less/package)
Cooling Time (days) 0 (Fresh Fuel)
-Loading a transport package with different types of nuclear fuel material is allowed for each reactor only when all the fuel elements contained are the same type having the same enrichment level.For the nuclear fuel material from JMTRC, however, mixed loading of fuel elements of different types and different enrichment levels is allowed.
- The values of weight and heat generation are calculated proportionally from the maximum weight and heat generation for each type of fuel element according to the number of assemblies contained.
(I)-Table A.1 Specification of nuclear material contained in shipping container (3/5) (Low Irradiated Fuel Element)
Reactor JMTRC JMTRC JMTRC JMTRC Fuel Element JMTRC Standard JMTRC Standard JMTRC Follower Special Follower Special Number of Spent Fuel Elements 10 or less (element/package)
Fuel Type HEU fuel MEU fuel Materials of Nuclear Fuel Uranium-aluminum alloy Uranium-aluminum dispersion alloy 235 U weight 2,850 1,990 3,170 2,860 2,100 (g or less/package)
U weight 3,180 2,220 7,210 6,500 4,780 (g or less/package)
Weight 235 U weight 285 199 317 286 210 (g or less/element)
U weight 6
318 222 721 650 478 (g or less/element)
Enrichment (wt% or less) 90.0 46.0 Total (GBq or ess/package) 17.3 (a) 234U: 16.2 Activity of (b) 235U: 0.25 Principal Radionuclide Contents (c) 236U: 0.29 (GBq or less/package)
(d) 238U: 0.05 (e) Others: 0.52 Physical State Solid Burn-up (% or less) 7.23x10-5 1.76x10-5 Total Heat Generation Rate 4.30x10-5 3.29x10-5 (W or less/package)
Cooling Time (days) 5,475 or more 1,460 or more
-Loading a transport package with different types of nuclear fuel material is allowed for each reactor only when all the fuel elements contained are the same type having the same enrichment level.For the nuclear fuel material from JMTRC, however, mixed loading of fuel elements of different types and different enrichment levels is allowed.
- The values of weight and heat generation are calculated proportionally from the maximum weight and heat generation for each type of fuel element according to the number of assemblies contained.
(I)-Table A.1 Specification of nuclear material contained in shipping container (4/5) (KUCA Fresh Fuel Element)
Reactor KUCA (Kyoto University Critical Assembly)
Fuel Element Coupon Flat Number of Fuel Elements 1,200 or less 300 or less (element/package)
Fuel Type LEU Fuel Uranium-molybdenum Uranium-silicon -aluminum Materials of Nuclear Fuel -aluminum dispersion dispersion alloy alloy 235 U weight (g or less/package) 4,800 4,500 U weight (g or less/package) 24,600 23,400 Weight 235 U weight (g or less/element) 4 15 U weight (g or less/element) 20.5 78 Enrichment (wt% or less) 19.95 Total (GBq or less/package) 15.5 7
234 U 14.5 Activity of 235 Principal Radionuclide U 0.38 Contents 236 (GBq or less/package) U 0.27 238 U 0.24 Physical State Solid Burn-up (% or less) 0 (Non-irradiated fresh Fuel)
Total Heat Generation Rate 0 (Non-irradiated fresh Fuel)
(W or less/package)
Cooling Time (days) 0 (Non-irradiated fresh Fuel)
-Loading a transport package with different types of nuclear fuel material is allowed for each reactor only when all the fuel elements contained are the same type having the same enrichment level.For the nuclear fuel material from JMTRC, however, mixed loading of fuel elements of different types and different enrichment levels is allowed.
- The values of weight and heat generation are calculated proportionally from the maximum weight and heat generation for each type of fuel element according to the number of assemblies contained.
- The absorbed dose rate to air at a position 1 m away from the surface of the package is 1 Gy/h or less.
(I)-Table A.1 Specification of nuclear material contained in shipping container (5/5) (Spectrum Converter)
Specification Material of Nuclear Fuel Uranium dioxide Physical State Solid (metal)
Plate Form Spectrum Converter Plate size (mm) 310 diam. x 10.7 thick Weight of plate (g or less) 2500 Number of plate (plates or less) 1 specification per 235 Weight U (kg or less) 1.002 Total (Bq or less) 3.5 x 108 8
Activity Principle Radionuclides (Bq 235 U 8.02x107 package or less)
Uranium Enrichment (wt % or less) 90 Heat Generation Rate (W or less) 5.13 x 10-6 Burn up Rate (%) 7.00 x 10-6 Cooling Time (days or more)
- 12340
- 1 : April 1st, 2021
- The absorbed dose rate to air at a position 1 m away from the surface of the package is 1 Gy/h or less.
Approximately 840 Inner shell lid Outer shell lid Eye-plate Outer shell main body Inner shell Main body Approximately 1800 Fuel basket Fuel element Main body
()-Fig.A.1 Rough drawing of package 9
Kinds of package
(I)-B. Kinds of package (1) Requirements for different kinds of package Since the radioactive substances stored are fresh fuel plates of uranium fuel and the radioactivity level exceeds the value of A2, this package must satisfy requirements for type BU package.
(2) Requirements for a fissile package Since this package contains fuel with an enrichment level between l9.95wt%
235 to 93.3wt% and more than 15g of U, it must satisfy requirements for fissile package.
Accordingly, this package corresponds to a type BU fissile package.
Packaging
(I)-C. Packaging
- 1. Outline of packaging This packaging is a cylindrical type in the form, which is maintained in vertical posture during both transport and handling.
The package outline is shown in ()-Fig.C.1.
The package tie down condition os shown in ()-Fig.C.2.
The package under transport condition is shown in ()-Fig.C.3.
The general feature of the packaging is as follows.
(1) The fuel basket of this packaging is designed to be rectangular type so that the rectangular fuel can be loaded (It is called fuel basket No.1). The Fuel basket No.2 has a disk-shaped fixing portion attached to the upper part of the fuel basket No.1 for the spectrum converter. Unless otherwise specified, these are collectively referred to as a fuel basket.
(2) The inner shell is designed as a pressure vessel against the design pressure of 9.81x10-2MPaGauge(1kgf/cm2).
(3) This packaging is handled by a crane using the eye-plate installed on the main body.
(4) To absorb impact energy caused by drop, there are the shock absorbers at the upper and lower parts of the packaging.
(5) To reduce the heat gain caused by fire, there are the heat insulators at the upper and lower parts of the packaging and shell.
(6) The containment boundary of this packaging is shown in ()-Fig.C.4.
1
Inner lid Outer lid Eye plate Outer main body Inner main body Fuel basket Fuel element Main body
()-Fig.C.1 Rough drawing of package 2
Transportation packaging Eye plate Lashing device
()-Fig.C.2 Package under transport condition 3
Ocean container Transportation shell Lashing device Side view Ocean container Transportation shell Lashing device Top view
()-Fig.C.3 Package under transport condition 4
Leak test orifice O-ring made by silicon rubber Inner shell lid bolts Weld Inner shell main body Weld The range that the surrounded with a slanted line shows a seal border.
()-Fig.C.4 Seal boundary of package 5
- 2. Structure of packaging (Refer to ()-Fig.C.5)
This packaging consists of 4 main parts:
(1) Main body (2) Inner lid (3) Fuel basket (4) Outer lid Following is the description of each part.
2.1 Main body (Refer to ()-Fig.C.6)
The main body is in the cylindrical shape of 1,559mm in height and 840mm in outer diameter and consists of the outer shell and inner shell.
The outer shell consists of 3mm thick stainless steel and 6mm thick stainless steel at the bottom. The inner shell consists of 10mm thick stainless steel and 35mm thick stainless steel at the bottom.
The shell and bottom plate is welded completely.
The space between the outer and inner shells, heat insulators and shock absorbers are applied to reduce the heat gain caused by fire and to absorb impact energy caused by drop.
At the upper side of the main body, the eye-plates are welded at 4 places to lift the packaging.
Eight fusible plugs is provided on the outer shell. These plugs are provided to avoid the pressure raise by steam or gas generated from the heat insulator and shock absorber due to heat during fire.
The inner shell is provided with three bosses at the upper side of the inner surface and the convex section at the bottom, in order to fix the fuel basket.
6
The boss and fuel basket upper part are fixed with bolts, and the fuel basket lower part is inserted into the convex section.
When fixing, to avoid metal contact of the inner shell and fuel basket, the cushion rubber is provided.
2.2 Inner lid (Refer to ()-Fig.C.7)
The inner lid is in the cylindrical shape, 62Omm in outer diameter and 55mm in thickness.
The inner lid is tied down with the main body, using 16 inner lid tightening bolts, and the contact section of the inner lid and inner shell is constructed so that leaktightness is maintained with O-ring. This O-ring is doubly provided to assure leaktightness, and a leak test hole between the double O-ring is provided to make it possible to perform a leak test.
2.3 Fuel basket (Refer to (()-Fig C.8, ()-Fig C.9)
The fuel basket No.1 is manufactured to locate each fuel element in the specified position of the packaging and maintain its relative position, and 10 fuel elements can be contained. The fuel basket No.1 is shown in ()-Fig.C.8 rectangular pipes to enclose the fuel elements, are assembled by welding, and the upper and the lower portions of the rectangular pipes, are welded to the flanges and basket bottom is attached to the flange bottom by the three bolts.
The inside dimension of the rectangular pipe is 94mmx94mm, the outside diameter of the fuel basket is 459mm, and the height is 1293mm.
The fuel basket No.2 is manufactured to locate the spectrum converter in the specified position of the packaging and maintain its relative position, and 1 spectrum converter can be contained. The fuel basket No.2 is shown in
()-Fig.C.9. The 10 rectangular pipes to enclose the fuel elements, are assembled by welding, and the upper and the lower portions of the rectangular pipes, are welded to the flanges and basket bottom is attached to the flange bottom by the 7
three bolts. In addition, the upper flange has disk-shaped space which is 329 mm in diameter to locate the spectrum converter. The inside dimension of the rectangular pipe is 94mmx94mm, the outside diameter of the fuel basket is 459mm, and the height is 1293mm.
And also, the fuel basket is fixed to the three bosses located at the upper inside portion of the inner shell by bolt, the movements to the vertical and circumferential direction are restricted, and the vibration is also restricted.
8
2.4 Outer lid (Refer to ()-Fig.C.10)
The outer lid is in of the cylindrical shape 398mm in height and 840mm in outer diameter.
The outer cover plate consists of 3mm thick stainless steel shell and 6mm thick stainless steel upper plate. The inner cover plate consists of 3mm thick stainless steels.
The space between the outer and inner cover plates, the heat insulators and shock absorbers are applied to reduce the heat gain caused by fire and to absorb impact energy caused by drop.
4 eye-bolt bosses for lifting are welded to the outer lid. 4 fusible plugs are provided on the outer cover plate. These plugs are used to avoid the pressure raise by steam or gas generated from the heat insulator and shock absorber due to heat during fire.
The outer lid is tied down with the outer lid tightening bolts through the rubber packing to the upper part of the main body in such a manner that it covers the inner lid. Such a structure prevents water from intruding into the clearance between the main body and the outer lid.
Also, the tightened section between the main body and outer lid can he sealed and locked.
9
(Outer lid O.D.) Outer shell lid Inner shell inner lid bolts (Inner lid O.D.)
Shock absorber material Inner shell Outer shell inner lid bolts Inner shell main body Outer shell main body Insulation material Shock absorber material
()-Fig.C.5 General drawing of package 10
Outer shell main body Inner shell main body Insulation material Shock absorber material
()-Fig.C.6 Main body 11
Positioning pin M24 bolt with the hexagon hole Leak test orifice O-ring The A part details
()-Fig.C.7 Inner shell lid 12
Upper part flange Square pipe Cushion rubber Lower part flange Lower part basket
()-Fig.C.8 Fuel Basket No.1 for box type fuel 13
()-Fig.C.9 Fuel Basket No.2 for Spectrum Converter 14
Outer cover plate Insulation material Shock absorber material Melting plug Inner cover plate
()-Fig.C.10 Outer shell lid 15
- 3. Material of packaging
() -Table C.1 shows the material of the packaging.
- 4. Dimension of packaging
() -Table C.2 shows the dimension of the packaging.
- 5. Weight of packaging
() -Table C.3 shows the weight of the packaging.
16
()-Table C.1 Material of packaging Name of Part Material Number Notes (1) Main body Outer shell Stainless steel 1S Inner shell Stainless steel 1S Eye plate Stainless steel 4 Boss Stainless steel 3 Heat insulator Hard polyurethane foam 1S Shock absorber Balsa wood 1S O-ring Silicone rubber 1S Fusible plug Solder, Stainless steel 8S Gasket Ethylene propylene rubber 1 (2) Inner Lid Inner Lid Stainless steel 1 (3) Fuel Basket Rectangular pipe Stainless steel 10 Upper flange Stainless steel 1 Lower flange Stainless steel 1 Cushion rubber Silicone rubber 1 (4) Outer Lid Outer cover plate Stainless steel 1S Inner cover plate Stainless steel 1S Heat insulator Hard polyurethane foam 1S Shock absorber Balsa wood 1S Fusible plug Solder, Stainless steel 4S 17
()-Table C.2 Dimension of packaging Name of Part Item Dimension(nominal) Notes (1) Main body Outer Diameter 840 Inner Diameter 460 Height 1,559 (2) Inner Lid Outer Diameter 620 Thickness 55 Size of Bolt M24 (3) Fuel Basket Outer Diameter 459 Height 1,293 Inner width 94x94 Disk-shaped space 329 Only basket No.2 diameter (4) Outer Lid Outer Diameter 840 Inner Diameter 630 Height 398 Size of Bolt M24 18
()-Table C.3 Weight of packaging No. Name Weight (kg) Notes 1 Inner shell main body 480 2 Inner shell lid 120 3 Fuel Basket 138 4 Outer shell lid 120 5 Total 858 The weights of the contents are shown in ()-Table D.1 and ()-Table D.2, the weight becomes maximum of 92kg when the ten JRR-3 standard fuel elements are contained and the maximum weight of the package is 950kg.
19
Contents of packaging
(I)-D. Contents of packaging D.1 Non-irradiated fresh fuel for research reactor Among the contents of packaging, non-irradiated fresh fuel elements for research reactors are plate type fuels to be charged in JRR-3, JRR-4, JMTR and KUR. There are three kind of enrichment, high-enriched uranium fuel (HEU fuel),
medium-enriched uranium fuel (MEU fuel), and low-enriched uranium fuel (LEU fuel).
The fuel meat is uranium aluminum alloy for HEU fuel, uranium aluminum dispersion type alloy for MEU fuel, and uranium aluminum dispersion type alloy or uranium silicon aluminum dispersion type alloy for LEU fuel.
Fuel plates are processed as follows : a fuel meat sandwiched by a frame and cover (cladding material) of aluminum alloy is hot-rolled. After being cold-rolled to the required thickness, it is cut longitudinally and transversely while being monitored by fluoroscopy so that the fuel meat can be located within the required zone.
On side plate or mounting plate of the aluminum alloy, the required number of grooves are provided for mounting the fuel plates. The width of a groove is equal to the thickness of the plate. Fuel plates are inserted into these grooves and mechanically fixed so that the fuel plates can resist a tensile stress of 265N/cm.
Required mounting parts are fixed by welding and other methods to complete a standard type fuel elements and follower type fuel elements (referred to as fuel elements hereinafter).
The fuel element is wrapped by some buffer, such as polyurethane foam, then put into an organic high-molecular compound bag such as polyethylene (Protective sheets), and loaded into the fuel basket of packaging.
When the fuel element are loaded, silicone rubber spacers are used to the upper and lower sides of the fuel element in order to absorb possible impact energy during transport, and also to fix the fuel element. For the KUR fuel elements, metal spacers (outer dimension : 84 x 90 x 875mm or 954mm) shown in (I)- Fig.
D.1 are inserted into the fuel basket, and the fuel elements are loaded into the 1
metal spacers.
The specifications of fuel elements loaded in the packaging are shown in
()-Table D.1.
D.2 Lowly irradiated fuel Among the contained fuels in the packaging, the lowly irradiated fuels are the plate type fuels loaded in the JMTRC, consisting of 61 HEU fuels and 31 MEU fuels. The core material of the fuel is the uranium-aluminum alloy for HEU fuel and is the uranium-aluminum dispersion type alloy for MEU. On the side plate or attachment plate made of aluminum alloy, are provided for the required number of the grooves corresponding to the thickness of the fuel plate. The fuel plate inserted is mechanically fixed by roll swage or fixed by the aluminum alloy pin to withstand the tensile force of more than 265N/cm.
The required parts are welded to the fuel plates to complete the standard fuel element, the special fuel element and the fuel follower (referred to as fuel elements etc. hereinafter).
The special fuel element has the structure where a part of the fuel plates are not mechanically fixed and can be removed. The fuel elements etc. are charged after cutting the unnecessary upper and lower portions to reduce the weight. For the special fuel elements, they are provide with a hold-down for fuel plate as shown in ()-Fig.D.13 through ()-Fig.D.15 and in ()-Fig.D.18.
The fuel elements etc. are packed with the shock absorber such as polyurethane foam etc. and is put in the bag made of organic high molecular compound such as polyethylene (protection sheet), and is enclosed in the fuel basket of the packaging.
In case the fuel element etc. are loaded, the spacers of silicone rubber are used at the top and bottom of the fuel element etc. in order to absorb the impact in the transportation and to fix the fuel element etc. by adjusting the position. The specification of the fuel element etc., used for the safety analysis of packaging is shown in ()-Table D.2.
2
D.3 Non-irradiated fresh fuel for KUCA Among the contents of packaging, fuels for critical assembly are fuel plate to be charged in KUCA. There are two types of fuels, a square plate fuel (coupon) and a flat plate fuel (flat), both of which are low-enriched uranium fuels (LEU fuel).
The fuel meat is a uranium molybdenum aluminum dispersion type alloy for coupon type, and a uranium silicon aluminum dispersion type alloy for flat type.
Coupon plates are processed as follows : a fuel meat is enclosed in a case and a cover (covering material) made of an aluminum alloy.
Flat plates are processed as follows : a fuel meat sandwiched by a frame and cover (cladding material) of aluminum alloy is hot-rolled. After being cold-rolled to the required thickness, it is cut longitudinally and transversely while being monitored by fluoroscopy so that the fuel meat can be located within the required zone.
The coupon plates are inserted into the aluminum sheath after sandwiching the cushion material such as aluminum sheet for protection between the fuel plates, and it is wrapped by some buffer such as polyurethane foam, then loaded into the fuel basket of packaging. The flat plates are wrapped by some buffer such as polyurethane foam after sandwiching the cushion material such as aluminum sheet for protection between the fuel plates, then loaded into the fuel basket of packaging.
When the KUCA fuels are loaded, silicone rubber spacers are used to the upper and lower sides of the fuel plates in order to absorb possible impact energy during transport, and also to fix the fuel plates.
The specifications of fuel elements loaded in the packaging are shown in
()-Table D.3.
3
D.4 Lowly irradiated high enriched uranium spectrum converter Among the contents of packaging, the spectrum converter is lowly irradiated high enriched uranium fuel and disk-shaped plate fuel which is charged in KUR heavy water facility as an experimental nuclear material and it is high enriched uranium fuel.
The fuel meat is uranium dioxide and the fuel meat is enclosed in 0.7 mm thickness cover made of an aluminum alloy.
The spectrum converter is loaded on disk-shaped space in fuel basket No.2.
When the spectrum converter is loaded, silicone rubber spacers are used to the upper and lower sides of the fuel plates in order to absorb possible impact energy during transport, and also to fix the spectrum converter.
The specifications of fuel elements loaded in the packaging are shown in
()-Table D.4.
4
(I)-Fig.D.1 Metal Spacer 5
()-Table D.1 Specification of fuel element (fresh fuel element)
Fuel Basket Type Box Type Reactor JRR-3 JRR-4 JMTR KUR Fuel JRR-3 JRR-3 JRR-4 JRR-4 JMTR JMTR KUR KUR KUR JRR-4 Element Standard Follower B L Standard Follower Standard Special Half-loaded Type Plate fuel Total no. of loaded 10 or less (fuel/Package)
Kind LEU fuel HEU fuel LEU fuel MEU fuel LEU fuel LEU fuel U-235 enrichment 19.95 or less 93.3 or less 19.95 or less 46.0 or less 19.95 or less 19.95 or less Nuclear spec.
(wt%)
U-235 contained 485 or less 310 or less 170 or less 230 or less 210 or less 320 or less 425 or less 280 or less 218 or less 109 or less 109 or less (g/one element)
U contained 5
2481 or less 1586 or less 183 or less 1177 or less 1075 or less 728 or less 2174 or less 1433 or less 1115 or less 558 or less 558 or less (g/one element)
Burnup (%) 0 (Fresh fuel)
Heat 0 (Fresh fuel) generation(w/container)
Cooling down days(day) 0 (Fresh fuel)
Radioactivity 29.8 or less (GBq/Package)
Uranium Uranium Uranium Uranium silicon Uranium silicon Uranium Uranium Uranium silicon Uranium Uranium silicon Uranium silicon silicon silicon silicon Core material alminum alminum alminum alloy alminum alminum alminum alminum alminum alminum alminum alminum dispersion alloy dispersion alloy dispersion alloy dispersion alloy dispersion alloy dispersion alloy dispersion alloy dispersion dispersion dispersion alloy alloy alloy Material Clad material Alminum alloy Side plate, Alminum alloy Attached plate Burnable Cadmium wire - Cadmium wire absorber Fuel cross Shape Rectangular type section shape Ref. drawing (I)-Fig.D.2 (I)-Fig.D.3 (I)-Fig.D.4 (I)-Fig.D.5 (I)-Fig.D.6 (I)-Fig.D.7 (I)-Fig.D.8 (I)-Fig.D.9 (I)-Fig.D.10 (I)-Fig.D.9 Fuel weight(kg/one 9.2 6.0 6.3 7.9 6.5 7.6 8.4 5.8 6.0 5.5 5.5 element)
()-Table D.2 Specification of fuel element (lowly irradiated fuel element)
Fuel Basket Type Box Reactor JMTRC Type JMTRC JMTRC JMTRC JMTRC JMTRC JMTRC Fuel Element Standard Special Follower Standard Special Follower Type Plate fuel Total no. of loaded 10 or less (fuel/Package)
Kind HEU fuel MEU fuel U-235 enrichment Nuclear spec.
90.0 or less 46.0 or less (wt%)
U-235 contained 285 or less 285 or less 199 or less 317 or less 286 or less 210 or less (g/one element)
U contained 318 or less 318 or less 222 or less 721 or less 650 or less 478 or less 6
(g/one element)
Burnup (%) 7.23x10-5 or less 1.76x10-5 or less
-5 Heat generation(w/container) 4.30x10 or less Cooling down days(day) 5475 or more 1460 or more (GBq/Package) 17.3 or less uranium uranium uranium Uranium alminum alminum alminum Core material Uranium Alminum alloy Uranium Alminum alloy Alminum dispersion dispersion dispersion Material alloy type alloy type alloy type alloy Clad material Alminum alloy Side plate, Alminum alloy Attached plate Burnable absorber - -
Fuel cross section Shape Rectangular type shape Ref. drawing (I)-Fig.D.11 (I)-Fig.D.12 (I)-Fig.D.13 (I)-Fig.D.14 (I)-Fig.D.15 (I)-Fig.D.16 (I)-Fig.D.17 (I)-Fig.D.18 (I)-Fig.D.19 Fuel weight(kg/one element) 6.3 6.6 2.0 6.9 4.1 6.7 6.9 4.4 Ref. drawing - (I)-Fig.D.13 (I)-Fig.D.14 (I)-Fig.D.15 - - (I)-Fig.D.18 -
Holder Weight
- 1.4 2.6 1.4 - - 1.4 -
(kg/one element)
()-Table D.3 Specification of fuel element (fresh fuel for KUCA)
Fuel Basket Type Box Reactor KUCA Type Fuel Element Coupon Flat Type Plate fuel Total no. of loaded 1200 or less 300 or less (fuel/Package)
Kind LEU fuel U-235 enrichment Nuclear spec.
19.95 or less (wt%)
U-235 contained 4 or less 15 or less (g/one plate) 7 U contained 20.5 or less 78 or less (g/one plate)
Burnup (%) 0 (Fresh fuel)
Heat generation(w/package) 0 (Fresh fuel)
Cooling down days(day) 0 (Fresh fuel)
(GBq/Package) 15.5 or less 15.5 or less Uranium molybdenum aluminum Uranium silicon aluminum Core material dispersion alloy dispersion alloy Material Clad material Aluminum alloy Side plate, Attached plate Burnable absorber -
Fuel cross section Shape Rectangular type shape Ref. drawing (I)-Fig.D.20 (I)-Fig.D.21 Fuel weight(kg/one plate) 36 230
()-Table D.4 Specification of fuel element (Spectrum converter)
Fuel Basket Box (with disk-shaped space)
Type Irradiated Experimental Nuclear Material Fuel Uranium Dioxide Type Plate fuel Total no. of loaded (fuel/
1 or less package)
Kind HEU fuel U-235 enrichment 90 or less Nuclear spec.
(wt%)
U-235 contained 1002 or less (g/one plate)
U contained 8
1115 or less (g/one plate)
Burnup (%) 7.00x10-6 Heat generation(w/package) 5.13x10-6 Cooling down days(day) 12340 (GBq/Package) 0.35 Core material Uranium dioxide Material Clad material Aluminum alloy Side plate, Attached plate Burnable absorber -
Fuel cross section Shape Disk shape Ref. drawing (I)-Fig.D.22 Fuel weight(kg/one plate) 2500
9
()-Fig.D.2 JRR-3 standard type fuel element (uranium silicon alminum dispersion alloy)
10
()-Fig.D.3 JRR-3 follower type fuel element (uranium silicon alminum dispersion alloy)
11
()-Fig.D.4 JRR-4B type fuel element
12
()-Fig.D.5 JRR-4L type fuel element
13
()-Fig.D.6 JRR-4 fuel element (uranium silicon alminum dispersion type alloy)
14
()-Fig.D.7 JMTR standard fuel element
15
()-Fig.D.8 JMTR follower type fuel element
After curving 69.33 70.67 (target for information t=1.52 (R=139.7 target for information) 625.5 Inner plate676.3 outer plate Fuel Plate Cladding Fuel Meat B C Fuel Plate Cross Section 16 Uranium silicon alminum dispersion Fuel plate 5 alloy 2 (outer) Aluminum alloy Uranium silicon alminum dispersion Fuel plate 4 alloy 16 (inner) Aluminum alloy 3 Handle Aluminum alloy 1 2 Side plate Aluminum alloy 2 1 nozzle Aluminum alloy 1 No. Name Material Q'ty View B Section A-A View C
()-Fig.D.9 KUR Standard and Half-loaded fuel elements Uranium silicon alminum dispersion alloy
After curving 69.33 70.67 (target for information t=1.52 (R=139.7 target for information) 625.5 Inner plate676.3 outer plate B C Fuel Plate Cladding Fuel Meat Fuel Plate Cross Section 17 Uranium silicon alminum Fuel plate 6 dispersion alloy 2 (outer) Aluminum alloy Uranium silicon alminum Fuel plate 5 dispersion alloy 7 (inner) Aluminum alloy 4 Middle plate Aluminum alloy 2 3 Side plate Aluminum alloy 2 Upper 1 2 Aluminum alloy Structural Part 1 Nozzle Aluminum alloy 1 View B Section A-A View C No. Name Material Q'ty
()-Fig.D.10 KUR Special fuel element Uranium silicon alminum dispersion alloy
18
()-Fig.D.11 JMTRC standard fuel element (A type, B type, C type)
19
()-Fig.D.12 JMTRC standard fuel element (pin fix type) (C type)
20
()-Fig.D.13 JMTRC special fuel element (special A type)
21
()-Fig.D.14 JMTRC special fuel element (special B type)
22
()-Fig.D.15 JMTRC special fuel element (special C type, special D type)
23
()-Fig.D.16 JMTRC fuel follower (HF type)
24
()-Fig.D.17 JMTRC standard fuel element (MA, MB, MC type)
25
()-Fig.D.18 JMTRC special fuel element (special MB type, special MC type)
26
()-Fig.D.19 JMTRC fuel follower (MF type)
27 Uranium molybdenum 2 Fuel meat aluminum dispersion alloy Aluminum alloy 1 Cladding (AG3NE)
No. Name Material
()-Fig.D.20 KUCA Coupon type fuel
28 Uranium silicon 2 Fuel meat aluminum dispersion alloy Aluminum alloy 1 Cladding (AG3NE)
No. Name Material
()-Fig.D.21 KUCA flat type fuel
29
()-Fig.D.22 Spectrum Converter