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IDENTIFICATION MARK J /2043/B(U) F COMPETENT AUTHORITY OF JAPAN CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1*9*9, ROPPONGI MINATO-KU TOKYO, JAPAN
IDENTIFICATION MARK J /2043/B(U) F COMPETENT AUTHORITY OF JAPAN CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1*9*9, ROPPONGI MINATO-KU TOKYO, JAPAN  


CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS This is to certify, in response to the application by Japan Atomic Energy Agency, that the package design described herein complies with the design requirements for a package containing Uranium Silicon Aluminum Dispersion Alloy, Uranium Aluminum Alloy and Uranium Aluminum Dispersion Alloy, specified in the 2018 Edition of the Regulations for the Safe Transport of Radioactive Material (International Atomic Energy Agency, Safety Standards Series No.SSR-6) and the Japanese rules based on the Act on Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors.
CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS This is to certify, in response to the application by Japan Atomic Energy Agency, that the package design described herein complies with the design requirements for a package containing Uranium Silicon Aluminum Dispersion Alloy, Uranium Aluminum Alloy and Uranium Aluminum Dispersion Alloy, specified in the 2018 Edition of the Regulations for the Safe Transport of Radioactive Material (International Atomic Energy Agency, Safety Standards Series No.SSR-6) and the Japanese rules based on the Act on Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors.
This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be transported.
This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be transported.
COMPETENT AUTHORITY IDENTIFICATION MARK: J/2043/B(U)F Ju /, 2 {       )/17 ), v Date                                 Hasegaw~su
COMPETENT AUTHORITY IDENTIFICATION MARK: J/2043/B(U)F Ju /, 2 {  
                                          ///
)/17 ), v Date Hasegaw~su  
Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval
///
Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval  


Reference of J/2043/B(U)F Page 1 of 6 Pages
Reference of J/2043/B(U)F Page 1 of 6 Pages
: 1. The Competent Authority Identification Mark : J/2043/B(U)F
: 1. The Competent Authority Identification Mark : J/2043/B(U)F
: 2. Name of Package                               : JRF-90Y-950K
: 2. Name of Package
: 3. Type of Package                               : Type B(U) package for fissile material
: 3. Type of Package
: 4. Specification of Package (1) Materials of Packaging (a) Main Body               : Stainless steel, Balsa wood and Hard polyurethane foam (b) Outer Lid              : Stainless steel, Balsa wood and Hard polyurethane foam (c) Inner Lid              : Stainless steel and Silicone rubber (d) Fuel Basket            : Stainless steel and Silicone rubber (2) Total Weight of Packaging                  : Approximately 860 kg (3) Outer Dimensions of Packaging (i) Outer Diameter                            : Approximately 840 mm (ii) Length                                  : Approximately 1,800 mm (4) Total Weight of Package                    : 950 kg or less (5) Illustration of Package                    : See Figure- I (Bird's-eye view)
: 4. Specification of Package (1) Materials of Packaging (a) Main Body (b) Outer Lid (c) Inner Lid (d) Fuel Basket (2) Total Weight of Packaging (3) Outer Dimensions of Packaging (i) Outer Diameter (ii) Length (4) Total Weight of Package (5) Illustration of Package
: JRF-90Y-950K
: Type B(U) package for fissile material
: Stainless steel, Balsa wood and Hard polyurethane foam
: Stainless steel, Balsa wood and Hard polyurethane foam
: Stainless steel and Silicone rubber
: Stainless steel and Silicone rubber
: Approximately 860 kg
: Approximately 840 mm
: Approximately 1,800 mm
: 950 kg or less
: See Figure-I (Bird's-eye view)
: 5.
: 5.
* Specification of Radioactive Contents       : See Table-I and Table-2
* Specification of Radioactive Contents
: See Table-I and Table-2
: 6. Description of Containment System Containment system consists of an inner shell and an inner lid (made of stainless steel). O-ring made of silicone rubber is used for the contact surface between the inner shell and the inner lid.
: 6. Description of Containment System Containment system consists of an inner shell and an inner lid (made of stainless steel). O-ring made of silicone rubber is used for the contact surface between the inner shell and the inner lid.
: 7. For Package Containing Fissile Materials,
: 7. For Package Containing Fissile Materials,  
' (1) Restrictions on Package (i) Restriction Number "N''                   : No restriction (ii) Array of Package                         : No restriction (iii) Criticality Safety Index (CSI)           :0 (2) Description of Confinement System
' (1) Restrictions on Package (i) Restriction Number "N''
: No restriction (ii) Array of Package
: No restriction (iii) Criticality Safety Index ( CSI)
: 0 (2) Description of Confinement System  


Reference of J/2043/B(U)F Page 2 of 6 Pages Confinement system consists of the basket which maintains the fuel elements contained in the package.
Reference of J/2043/B(U)F Page 2 of 6 Pages Confinement system consists of the basket which maintains the fuel elements contained in the package.
Line 50: Line 69:
: 8. For Type B (M) Packages, a Statement Regarding Prescriptions of Type B (U)
: 8. For Type B (M) Packages, a Statement Regarding Prescriptions of Type B (U)
Package that do not apply to this Package Not applicable (This package is Type B(U))
Package that do not apply to this Package Not applicable (This package is Type B(U))
: 9. Assumed Ambient Conditions (i) . A.mbient Temperature Range               : *40°C~38°C (ii) Insolation Data                            : Table 12 of IAEA Regulation
: 9. Assumed Ambient Conditions (i). A.mbient Temperature Range (ii) Insolation Data
: 10. Handling, Inspection and Maintenance (1) Handling Instructions (i) Package should be handled carefully in accordance with the schedule and procedures established properly taking all possible safety measures .
: 10. Handling, Inspection and Maintenance (1) Handling Instructions
  . (ii) Package should be handled using appropriate lifting devices and cranes.
: *40°C~38°C
: Table 12 of IAEA Regulation (i) Package should be handled carefully in accordance with the schedule and procedures established properly taking all possible safety measures.  
. (ii) Package should be handled using appropriate lifting devices and cranes.
(iii) When packaging is stored outdoors, it shoul,;l be covered with an appropriate waterproof sheet, avoiding the situation where it is placed directly on.the ground.
(iii) When packaging is stored outdoors, it shoul,;l be covered with an appropriate waterproof sheet, avoiding the situation where it is placed directly on.the ground.
(2) Inspections and Maintenance of Packaging The following inspections should be performed not less than once a year (once for every ten times in a case where the packaging is used more than ten times a year) and defect of packaging should be repaired, if any, in order to maintain the integrity of packaging.
(2) Inspections and Maintenance of Packaging The following inspections should be performed not less than once a year (once for every ten times in a case where the packaging is used more than ten times a year) and defect of packaging should be repaired, if any, in order to maintain the integrity of packaging.
(i) Visual Appearance Inspection (ii) Pressure Durability Inspection (iii) Maintenance of O*ring Used for Containment System (iv) Leakage Rate Measurement Inspection
(i) Visual Appearance Inspection (ii) Pressure Durability Inspection (iii) Maintenance of O*ring Used for Containment System (iv) Leakage Rate Measurement Inspection  
  , (v) Subcriticality Inspection (vi) Lifting Inspection (3) Actions Prior to Shipment The following inspections should be performed prior to shipment.
, (v) Subcriticality Inspection (vi) Lifting Inspection (3) Actions Prior to Shipment The following inspections should be performed prior to shipment.
(i) Visual Appearance Inspection
(i) Visual Appearance Inspection  


Reference of J/2043/B(U)F Page 3 of 6 Pages (ii) Lifting Inspection (iii) Weight Measurement Inspection (iv) Surface Contamination Measurement Inspection (v) Radiation Dose Rate Inspection (vi) Subcriticality Inspection (vii) Contents Specification Check Inspection (viii) Leakage Rate Measurement Inspection (4) Precautions for Loading of Package for Shipment Package should be securely loaded to the conveyance at the designated tie-down portion of the package so as not to move; roll down or fall down from the loading position during transport.
(ii) Lifting Inspection (iii) Weight Measurement Inspection (iv) Surface Contamination Measurement Inspection (v) Radiation Dose Rate Inspection
: 11. Issue Date and Expiry Date (i) Issue Date         : May 23, 2022 (ii) Expiry Date       : May 22, 2082
( vi) Subcriticality Inspection (vii) Contents Specification Check Inspection (viii) Leakage Rate Measurement Inspection (4) Precautions for Loading of Package for Shipment Reference of J/2043/B(U)F Page 3 of 6 Pages Package should be securely loaded to the conveyance at the designated tie-down portion of the package so as not to move; roll down or fall down from the loading position during transport.
: 11. Issue Date and Expiry Date (i) Issue Date
: May 23, 2022 (ii) Expiry Date
: May 22, 2082  


Reference of J/2043/B(U)F Page 4 of 6 Pages c/>840 Inner Lid Outer Lid Eye Plate Outer Shell Inner Shell 0
0 0
0 Fuel Basket 00                                      *' *'
00 c/>840 Reference of J/2043/B(U)F Page 4 of 6 Pages Inner Lid Outer Lid Eye Plate Outer Shell Inner Shell Fuel Basket Fuel Element Main Body (Unit: mm)
Fuel Element Main Body (Unit: mm)
Figure-I Illustration of JRF-90Y-950K Package (Bird's-eye view)  
Figure-I Illustration of JRF-90Y-950K Package (Bird's-eye view)


Table* 1       Specification of Contents (Fresh Fuel Eiement)
Table* 1 Specification of Contents (Fresh Fuel Eiement)
Reactor                                                 JRR*3                                                                       JMTR Type                                                     JRR*3                                   JRR*3                                   JMTR                                 JMTR Fuel Element                                                                  Follower                                 Standard                           Follower Standard Number of Fuel Elements                                                                                           10 or less (element/Packae:e)
Reactor JRR*3 JMTR Type Fuel Element JRR*3 JRR*3 JMTR JMTR Standard Follower Standard Follower Number of Fuel Elements 10 or less (element/Packae:e)
Fuel Type                                                       LEU fuel                                                                   LEU fuel Material of Nuclear Fuel                         Uranium .Silicon Aluminum Disuersion Allov                                   Uranium Silicon Aluminum Disuersion Allov Physical State                                                                                             Solid 235 U weight 4,850                                   3,100                                   4,250                               2,800 (e: or less/packae:e)
Fuel Type LEU fuel LEU fuel Material of Nuclear Fuel Uranium.Silicon Aluminum Disuersion Allov Uranium Silicon Aluminum Disuersion Allov Physical State Solid 235U weight (e: or less/packae:e) 4,850 3,100 4,250 2,800 Uweight 24,810 15,860 21,740 14,330 (e: or less/uackae:e)
Uweight                           24,810                                 15,860                                   21,740                               14,330 (e: or less/uackae:e)
Weight 235U weight (e: or less /element) 485 310 425 280 Uweight (e: or less /element) 2,481 1,586 2,174 1,433 Enrichment(wt% or less) 19.95 19.95  
Weight               235 U weight 485                                     310                                     425                                 280 (e: or less /element)
. Total 29.8 (GBq or less/uackae:e)
Uweight                            2,481                                   1,586                                   2,174                               1,433 (e: or less /element)
Activity 2a<u 28.6 of Principal Radionuclide 2asu 0.38 Contents (GBq or less/package) 236U 0.59
Enrichment(wt% or less)                                                       19.95                                                                       19.95
'"U 0.24 Burn*up (% or less) 0 (Fresh fuel)
                          . Total 29.8 (GBq or less/uackae:e)
Total Heat Generation Rate 0 (Fresh fuel)
Activity                                                                                                           2a<u       28.6 of                                                                                                             2asu       0.38 Principal Radionuclide Contents                                                                                                           236U      0.59 (GBq or less/package)
                                                                                                                    '"U       0.24 Burn*up (% or less)                                                                                       0 (Fresh fuel)
Total Heat Generation Rate                                                                                     0 (Fresh fuel)
(W or less /Packae:e)
(W or less /Packae:e)
Cooline: time (DavJ                                                                                     0 (Fresh fue 1l                                                                             fu"
Cooline: time (DavJ 0 (Fresh fue 1l fu"  
*Loading a transport package with different types of fuel-element is allowed for each reactor only when all the fuel elements contained are the same material of nuclear fuel having the same enrichme:q.t     ""
*Loading a transport package with different types of fuel-element is allowed for each reactor only when all the fuel elements contained are the same material of nuclear fuel having the same enrichme:q.t  
                                                                                                                                                                                                              ~
~
(1) level.                                                                                                                                                                                                       ~
(1) level.  
                                                                                                                                                                                                          'd   (1)
~  
- 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. crq  PJ   O (1) 0...
'd (1)  
01   ;;a O
- 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.
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Table*2
Type Reactor Fuel Element Number of Fuel Elements (element/Packa,rn)
Fuel Tvne Material of Nuclear Fuel Phvsical State 235U weight
(,,, or less/nackalle)
Uweight (g or less/package)
Weight 235U weight (e: or less /element)
Uweight
(,,, or less /element)
Enrichment(wt% or less)
Total (GBo or less/nackae:e)
Activity of Principal Radionuclide Contents (GBq or less/package)
Burn*un (% or less)
Total Heat Generation Rate (W or less /Packalle)
Cooline: time Table*2
* Specification of Contents (Low Irradiated Fuel Element)
* Specification of Contents (Low Irradiated Fuel Element)
Reactor                                                                                        JMTRC Type              Fuel Element                          Special                                 Standard                                   Special                           Follower Number of Fuel Elements                                                                                            10 or less (element/Packa,rn)
JMTRC Special Standard Special 10 or less HEU fuel MEUfuel Uranium Aluminum Uranium Aluminum Dispersion Alloy Allov Solid 2,850 3,170 2,860 3,180 7,210 6,500 285 317 286 318 721 650 90.0 46.0 17.3 2s*u 16.2 2ssu 0.25 2ssu 0.29 2sau 0.05 Other : 0.52 7.23 X 10*5 l.76X 10*5 4.30X 10*5 3.29X 10*5 5,475 Dav or more 1,460 Dav or more Follower 2,100 4,780 210 478
Fuel Tvne          .                      HEU fuel                                                                       MEUfuel Uranium Aluminum                                                   Uranium Aluminum Dispersion Alloy Material of Nuclear Fuel                                  Allov Phvsical State                                  .                                                            Solid 235U weight 2,850                                   3,170                                   2,860                               2,100
~
(,,, or less/nackalle)                                                                                                                                                        .
ib' a
Uweight                              3,180                                   7,210                                   6,500                               4,780 (g or less/package)
-Loading a transport package with *different types of fuel element is allowed for each reactor* only when all the fuel elements. contained are the same material of nuclear fuel_having the same enrichr&#xb5;ent  
Weight                235U weight 285                                       317                                     286                                 210 (e: or less /element)                    .
~
Uweight                                318                                       721                                     650                               478
level. However, loading with different types of fuel element is allowed even-if fuel elements contained are different type or different enrichment level, in case of JMTRC fuel element,  
(,,, or less /element)
~ ~  
Enrichment(wt% or less)                                    90.0                                                                         46.0 Total                                                                                          17.3 (GBo or less/nackae:e)                                                                                                                                      .
~ ~  
Activity                                                                                                            2s*u       16.2 of                                                                                                              2ssu       0.25 Principal Radionuclide                                                                                2ssu       0.29 Contents (GBq or less/package) 2sau       0.05 Other : 0.52 Burn*un (% or less)                              7.23 X 10* 5                                                                   l.76X 10*5 Total Heat Generation Rate                              4.30X 10*5                                                                     3.29X 10*5 (W or less /Packalle)                                                                                                                              .
" 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 asse_mblies contained.  
                                                                                                                                                                                                                  ~
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1,460 Dav or more                                                           ib' Cooline: time                            5,475 Dav or more
-Loading a transport package with *different types of fuel element is allowed for each reactor* only when all the fuel elements. contained are the same material of nuclear fuel_having the same enrichr&#xb5;ent a~
level. However, loading with different types of fuel element is allowed even-if fuel elements contained are different type or different enrichment level, in case of JMTRC fuel element,
                                                                                                                                                                                                            ~ ~
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" 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 asse_mblies contained.         ~ ~
* The absorbed dose ra&#xa5;l to air at a position*! m away. from the surface of the package is 1 Gy/h or less.
* The absorbed dose ra&#xa5;l to air at a position*! m away. from the surface of the package is 1 Gy/h or less.
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Latest revision as of 10:07, 27 November 2024

Part 1-Response, Acceptance Review, 2/23/23, Document No. 1 Japanese Certificate of the Competent Authority No. J/2043/B(U)F, Model No. JRF-90Y-950K (English Version) Issued on May 23, 2022
ML23058A286
Person / Time
Site: 07103036
Issue date: 07/29/2022
From: Kiyomitsu H
Govt of Japan, Nuclear Regulation Authority
To:
Storage and Transportation Licensing Branch
Shared Package
ML23058A255 List:
References
CAC 001794, EPID L-2023-DOT-0000, J /2043/B(U) F
Download: ML23058A286 (10)
v • d • e


Text

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IDENTIFICATION MARK J /2043/B(U) F COMPETENT AUTHORITY OF JAPAN CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS ISSUED BY NUCLEAR REGULATION AUTHORITY 1*9*9, ROPPONGI MINATO-KU TOKYO, JAPAN

CERTIFICATE FOR APPROVAL OF PACKAGE DESIGN FOR THE TRANSPORT OF RADIOACTIVE MATERIALS This is to certify, in response to the application by Japan Atomic Energy Agency, that the package design described herein complies with the design requirements for a package containing Uranium Silicon Aluminum Dispersion Alloy, Uranium Aluminum Alloy and Uranium Aluminum Dispersion Alloy, specified in the 2018 Edition of the Regulations for the Safe Transport of Radioactive Material (International Atomic Energy Agency, Safety Standards Series No.SSR-6) and the Japanese rules based on the Act on Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. This certificate does not relieve the consignor from compliance with any requirement of the government of any country through or into which the package will be transported. COMPETENT AUTHORITY IDENTIFICATION MARK: J/2043/B(U)F Ju /, 2 { )/17 ), v Date Hasegaw~su /// Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval

Reference of J/2043/B(U)F Page 1 of 6 Pages

1. The Competent Authority Identification Mark : J/2043/B(U)F
2. Name of Package
3. Type of Package
4. Specification of Package (1) Materials of Packaging (a) Main Body (b) Outer Lid (c) Inner Lid (d) Fuel Basket (2) Total Weight of Packaging (3) Outer Dimensions of Packaging (i) Outer Diameter (ii) Length (4) Total Weight of Package (5) Illustration of Package
JRF-90Y-950K
Type B(U) package for fissile material
Stainless steel, Balsa wood and Hard polyurethane foam
Stainless steel, Balsa wood and Hard polyurethane foam
Stainless steel and Silicone rubber
Stainless steel and Silicone rubber
Approximately 860 kg
Approximately 840 mm
Approximately 1,800 mm
950 kg or less
See Figure-I (Bird's-eye view)
5.
  • Specification of Radioactive Contents
See Table-I and Table-2
6. Description of Containment System Containment system consists of an inner shell and an inner lid (made of stainless steel). O-ring made of silicone rubber is used for the contact surface between the inner shell and the inner lid.
7. For Package Containing Fissile Materials,

' (1) Restrictions on Package (i) Restriction Number "N

No restriction (ii) Array of Package
No restriction (iii) Criticality Safety Index ( CSI)
0 (2) Description of Confinement System

Reference of J/2043/B(U)F Page 2 of 6 Pages Confinement system consists of the basket which maintains the fuel elements contained in the package. (3) Assumptions of Leakage of Water into Package It is assumed in criticality analysis that water will leak into void space of the inner shell. (4) Special Features in Criticality Assessment Not applicable

8. For Type B (M) Packages, a Statement Regarding Prescriptions of Type B (U)

Package that do not apply to this Package Not applicable (This package is Type B(U))

9. Assumed Ambient Conditions (i). A.mbient Temperature Range (ii) Insolation Data
10. Handling, Inspection and Maintenance (1) Handling Instructions
*40°C~38°C
Table 12 of IAEA Regulation (i) Package should be handled carefully in accordance with the schedule and procedures established properly taking all possible safety measures.

. (ii) Package should be handled using appropriate lifting devices and cranes. (iii) When packaging is stored outdoors, it shoul,;l be covered with an appropriate waterproof sheet, avoiding the situation where it is placed directly on.the ground. (2) Inspections and Maintenance of Packaging The following inspections should be performed not less than once a year (once for every ten times in a case where the packaging is used more than ten times a year) and defect of packaging should be repaired, if any, in order to maintain the integrity of packaging. (i) Visual Appearance Inspection (ii) Pressure Durability Inspection (iii) Maintenance of O*ring Used for Containment System (iv) Leakage Rate Measurement Inspection , (v) Subcriticality Inspection (vi) Lifting Inspection (3) Actions Prior to Shipment The following inspections should be performed prior to shipment. (i) Visual Appearance Inspection

(ii) Lifting Inspection (iii) Weight Measurement Inspection (iv) Surface Contamination Measurement Inspection (v) Radiation Dose Rate Inspection ( vi) Subcriticality Inspection (vii) Contents Specification Check Inspection (viii) Leakage Rate Measurement Inspection (4) Precautions for Loading of Package for Shipment Reference of J/2043/B(U)F Page 3 of 6 Pages Package should be securely loaded to the conveyance at the designated tie-down portion of the package so as not to move; roll down or fall down from the loading position during transport.

11. Issue Date and Expiry Date (i) Issue Date
May 23, 2022 (ii) Expiry Date
May 22, 2082

0 0 00 c/>840 Reference of J/2043/B(U)F Page 4 of 6 Pages Inner Lid Outer Lid Eye Plate Outer Shell Inner Shell Fuel Basket Fuel Element Main Body (Unit: mm) Figure-I Illustration of JRF-90Y-950K Package (Bird's-eye view)

Table* 1 Specification of Contents (Fresh Fuel Eiement) Reactor JRR*3 JMTR Type Fuel Element JRR*3 JRR*3 JMTR JMTR Standard Follower Standard Follower Number of Fuel Elements 10 or less (element/Packae:e) Fuel Type LEU fuel LEU fuel Material of Nuclear Fuel Uranium.Silicon Aluminum Disuersion Allov Uranium Silicon Aluminum Disuersion Allov Physical State Solid 235U weight (e: or less/packae:e) 4,850 3,100 4,250 2,800 Uweight 24,810 15,860 21,740 14,330 (e: or less/uackae:e) Weight 235U weight (e: or less /element) 485 310 425 280 Uweight (e: or less /element) 2,481 1,586 2,174 1,433 Enrichment(wt% or less) 19.95 19.95 . Total 29.8 (GBq or less/uackae:e) Activity 2azj

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