Matsuoka et al., 2001 - Google Patents
Verification of packages containment system using metallic gasket to comply with requirement for both transport and storageMatsuoka et al., 2001
- Document ID
- 6157151863586440574
- Author
- Matsuoka T
- Kuri S
- Ohsono K
- Hode S
- Maruoka K
- Akamatsu T
- Minami M
- Publication year
- Publication venue
- Revised Proc. PATRAM
External Links
Snippet
Mitsubishi Heavy Industries, Ltd.(MHI) has developed a transportable storage cask design; the" MSF series". The MSF series casks adopt metallic gaskets for both transportation and storage containment devices. In Japan, metallic gaskets are selected for storage cask as …
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
- G21F5/12—Closures for containers; Sealing arrangements
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US10128012B2 (en) | Method of using a modular container system for radioactive waste | |
US11373773B2 (en) | Method for making containment cask for drum containing radioactive hazardous waste | |
JP2004525377A (en) | Improved container for transporting uranium hexafluoride | |
US5464988A (en) | Tritium waste package | |
US4810890A (en) | Package for the shipment of dangerous materials | |
Matsuoka et al. | Verification of packages containment system using metallic gasket to comply with requirement for both transport and storage | |
KR100967391B1 (en) | Dedicated transport container for receiving and transporting waste resin or concentrated waste radioactive waste | |
US20220208405A1 (en) | High level waste transport system with containment feature | |
JPH032696A (en) | Air borne transportation container for nuclear fuel | |
KR100946242B1 (en) | How to evaluate the safety of radioactive waste containers | |
O’hira et al. | Design study of a tritium transport package for future fusion reactors | |
Shen et al. | The Optimization Design of Storage Efficiency and Structural Analysis for the 3 Cubic Meter Radioactive Waste Container | |
Itoh et al. | Immersion tests for cask transporting vitrified high-level radioactive waste | |
JP2004093507A (en) | Recycle fuel assembly containment vessel | |
Rossmassler et al. | Tritium waste package | |
Snow et al. | Drop testing of DOE spent nuclear fuel canisters | |
Marsden et al. | Autoradiolysis of Tritiated Water Adsorbed on Molecular Sieve | |
Gowing et al. | Development of the BNFL Vitrified Residue Transport Flask | |
Choi et al. | Determination of prerequisites for the estimation of transportation cost of spent fuels | |
Ammerman et al. | Testing in support of transportation of residues in the pipe overpack container | |
UTOiBUtlffN | Directory of Certificates of Compliance for Radioactive Materials Packages | |
McCarthy | Hanford Site radioactive hazardous materials packaging directory | |
Cruse | TRUPACT-2 design, testing and certification | |
Baroux et al. | Operational experience of TN 24 dual purpose spent fuel storage casks at the DOEL nuclear power plants in Belgium | |
Sievwright et al. | Development of sealed Type B transport containers for the transport of intermediate level radioactive waste |