ML23101A032
| ML23101A032 | |
| Person / Time | |
|---|---|
| Site: | 07103004 |
| Issue date: | 04/03/2023 |
| From: | Boyle R, Kiyomitsu H, Neely R Edlow International Co, Govt of Japan, Nuclear Regulation Authority, US Dept of Transportation (DOT), Office of Hazardous Materials Safety |
| To: | Division of Fuel Management |
| Shared Package | |
| ML23100A181 | List: |
| References | |
| Download: ML23101A032 (9) | |
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IDENTIFICATION MARK J/2044/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 Medium Enriched Uranium Fuels(Spent Fuel Elements) and Low Enriched Uranium Fuels(Spent Fuel Elements), 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/2044/B(U)F Director, Division of Licensing for Nuclear Fuel Facilities Secretariat of Nuclear Regulation Authority Competent Authority of JAPAN for Package Design Approval
Reference of J/2044/B(U)F Page 1 of 5 Pages
- 1. The Competent Authority Identification Mark : J/2044/B(U)F
- 2. Name of Package : JMS*87Y*l8.5T
- 3. Type of Package : Type B(U) package for fissile material
- 4. Specification of Package (1) Materials of Packaging (a) Body and Lid : Stainless steel (b) Basket : Stainless steel and Boral plate (c) Shock absorber : Stainless steel and Fir-plywood (2) Total Weight of Packaging : 18,110 kgor less (3) Outer Dimensions of Packaging (i) Outer Diameter : Approximately 1,900 mm (ii) Height : Approximately 2,000 mm (4) Total Weight of Package : 18,440 kg or less (5) Illustration of Package : See Figure* 1 (Cutaway view)
- 5. Specification of Radioactive Contents : See Table*l
- 6. Description of Contaimnent System Contaimnent system consists of the body, the lid, inside the lid O*ring, the vent plug and the drain valve.
Silicone rubber is used for contact surface of body and lid, body and vent plug , body and drain valve and the valve seat.
- 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 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 spaces of inner packaging.
(4) Special Features in Criticality Assessment Not applicable
Reference of J/2044/B(U)F Page 2 of 5 Pages
- 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) Ambient Temperature Range : *40°C-38°C (ii) Insolation Data : Table 12 ofIAEA Regulation
- 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.
(ii) Package should be handled using appropriate lifting devices and the crane.
(iii) When packaging is stored outdoors, it should 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 Inspection (ii) Pressure Measurement Inspection (iii) Leak Tightness Inspection (iv) Maintenance of O*rings, Valve, etc., used for Containment System (v) Shielding Inspection (vi) Subcriticality Inspection (vii) Heat Transfer Inspection (viii) Lifting Inspection (3) Actions Prior to Shipment The following inspections should be performed prior to shipment.
(i) Visual Inspection (ii) Lifting Inspection (iii) Weight Inspection (iv) Surface Contamination Inspection (v) Dose Rate Inspection (vi) Subcriticality Inspection (vii) Contents Inspection (viii) Surface Temperature Inspection (ix) Leak Tightness Inspection (x) Pressure Inspection (4) Precautions for Loading of Package for Shipment
Reference of J/2044/B(U)F Page 3 of 5 Pages Package should be securely loaded to the conveyance at the designated tie-down portion of the packaging 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 : Sep 21, 2022 (ii) Expiry Date : Sep 20, 2062 However, if this certificate no longer meets the technical standards (limited to those related to the design of package) due to a revision of the regulations* 1,2, this certificate will be expired.
- 1 The NRA Ordinance on Off-Site Transportation of Nuclear Fuel Materials, etc.
(Ministerial ordinance issued by the Prime Minister's Office No. 57 of 1978)
- 2 The Notification on Technical Details for Off-Site Transportation of Nuclear Fuel Materials, etc. (Notice issued by Science and Technology Agency No. 5 of 1990)
Reference of J/2044/B(U)F Page 4 of 5 Pages Upper shock absorber Bolts for fastenin u er shock absorber Proximity prevention frame Lid Bolts for fastening lid Vent plug Lug for seal Lifting lug Tie-down lug Cask body 0
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g Fins
~ Basket Bottom fin Drain valve Bolts for fastening bottom Bottom shoe shoc k absorber Approx. 1900 .
(Unit: mm)
Figure*l Illustration of JMS*87Y*l8.5T Package (Cutaway view)
Table* I Specification of Radioactive Contents Medium Enriched Uranium Fuels Low Enriched Uranium Fuels (LEU)
(MEU)(Spent Fuel Elements) (Snent Fuel Elements)
~ n t JMTR Standard Fuel JMTR Standard Fuel JMTR Follower Fuel T Elements (MEU) Elements (LEU) Elements (LEU)
Reactor JMTR JMTR Fuel Tyne Plate Fuel Plate Fuel Number of Fuel Elements 30 or less 30 or less (elements/Package)
Enrichment 46.0 or less 19.95 or less (wt%)
Initial 235U weight 302 or less 315.6 or less 450 or less Value (e: /element)
U weight 719 or less 2338 or less 1569 or less (e: /element)
Burn-un (%) 40 or less 50 or less 60 or less 50 or less 60 or less Cooline: Time (davsl' 360 or more 420 or more 540 or more 420 or more 540 or more Condition Solid Solid Total l.78Xl0 4 2.43Xl04 2.12XlO4 l.63Xl04 l.43Xl04 (TBa /30 elements) 9DSr : 7.47x1O2 90 Sr : 5.O4xlO 2 95Zr : 1.O2x10a 95Zr : 8.28x 102 95Zr : 5.56Xl0 2 goy goy : 7.47x102 :5.O4Xl02 Activity of 95Nb :2.21Xl03 95Nb :l.76xl03 95Nb : l.18X 103 Principal 137Cs: 7.74x102 137 Cs:5.22x102 Contents 144Ce:4.98xl03 1**Ce:7.4lxl03 144Ce: 4.97x 10 3 Radionuclide 144 Ce: 6.63xl0 3 144Ce: 4.4 7x 103 144Pr: 4.98XlO 3 144Pr:7.4lxl03 144Pr: 4.97x 10 3 (TBq /30 elements) 144Pr: 6.63X 103 147 Pm:9.68xl0 2 . 144Pr:4.47XlO 3 147Pm: 1.OOxiO3 147Pm: l.44Xl03 147Pm: l.4Oxl03 147Pm:9.43x102 Uranium*Aluminum Dispersion Uranium*Silicon*Aluminum Dispersion Alloy Fuel Core Allov Material Cladding and Aluminum Alloy Aluminum Alloy ~
Side Plate tt'
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Total Heat Generation Rate (kW/3O elements) 1.98 2.80 I 2.40 I 1.88 I
- Each package shall be loaded with single fuel (i.e. only one kind of "Spent Fuel Elements") or mixed fuels (i.e. two or more kinds of "Spent Fuel Elements")
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- The absorbed dose rate to air at a position 1 m away from the surface of the package is 1 Gy/h or more.
- This is the period set for the design of the package, and since there will be no additional spent fuel in the future, the minimum number of cooling time for tlae fuel to be transported is 5800 days or more. As of August 2022, the radioactivity intensity has decreased by about 90%.
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