Safeguards in the prototype fast breeder reactor MONJU
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:217895
- Power Reactor and Nuclear Fuels Development Corporation, Ibaraki-ken (Japan)
MONJU is a prototype fast breeder reactor in Japan designed to have a 280-MW(electric) output. The Power Reactor and Nuclear Fuel Development Corporation (PNC) started its construction in the autumn of 1985 in Tsuruga. The loading of the core fuel assemblies was started in October 1993, and the preoperational test is ongoing. MONJU uses 198 mixed-oxide (MOX) fuel assemblies as core fuel and 172 depleted uranium assemblies as blanket fuel. Assemblies loaded in-core and stored in the ex-vessel storage tank (EVST) reside in liquid sodium. These plutonium-containing fuel assemblies, MOX, and irradiated depleted uranium are regarded as in the difficult-to-access area, and the flows of fuel assemblies into and out of the area must be verified. Flow is verified by fuel flow monitors measuring radiation, which can limit inspector attendance during fuel handling.
- OSTI ID:
- 217895
- Report Number(s):
- CONF-9509215--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: Suppl.1 Vol. 72; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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