Development of MONJU spent fuel cask for post irradiation examination
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
A cask, type B(M), for transporting fuel irradiated in the prototype FBR 'Monju' to the PIE facility is being developed by Power Reactor and Nuclear Fuel Development Corporation (PNC). The PIE facility will be constructed at PNC's O-arai Engineering Center (OEC) and the fuel will be transported by sea. Three fuel assemblies canned with water or one fuel assembly encapsulated in a specially designed inner container with helium gas can be contained in the cask. For the multiple use of the cask, it is considered that the cask can also accomodate the ATR 'Fugen' and demonstration fuel. The following remain to be done; (1) handling test of an inner container (2) demonstration tests with scale models under normal and accidental conditions (3) preparation for design approval (4) fabrication The cask is scheduled to be used in 1994. (author)
Additional details
Publishing Information
- Journal Title
- Donen Giho
- Journal Issue
- no.71
- Series
- Donen Giho.
- ISSN
- 0289-6605
- CODEN
- DOGIE
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 21024243
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- AFTER-HEAT REMOVAL; CASKS; FUEL ASSEMBLIES; IMPACT TESTS; MARITIME TRANSPORT; MONJU REACTOR; PLANNING; POST-IRRADIATION EXAMINATION; SAFETY; SEALS; SPECIFICATIONS; SPENT FUELS
- Descriptors DEC
- BREEDER REACTORS; CONTAINERS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL TESTS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; TESTING; TRANSPORT