Experience in the reprocessing of mixed-oxide fuels at PNC (Power Reactor and Nuclear Fuel Development Corporation)

Conference · Sat Dec 31 23:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6393306

Komatsu, Hisato; Onishi, Moichi; Araya, Sadao; Fukushima, Misao

The Power Reactor and Nuclear Fuel Development Corporation (PNC) in Japan has experience in reprocessing mixed-oxide (MOX) fuels for the advanced thermal reactor (ATR) Fugen at the Tokai Reprocessing Plant (TRP) and for fast breeder reactors (FBRs) at the Chemical Processing Facility (CPF). The TRP was originally designed and constructed as the first reprocessing plant for light water reactor fuels in Japan. It has processed {approximately}400 t of spent fuels since 1977. To utilize recovered plutonium, PNC has developed the prototype ATR Fugen. This reactor has been operated using MOX fuel since 1978. In parallel, utilities are promoting a plutonium thermal project. Several MOX assemblies have already been loaded in a boiling water and a pressurized water reactor. To facilitate the operation of Fugen and promote research and development for the reprocessing of MOX fuels in Japan, PNC obtained a license for reprocessing fuels for Fugen at TRP in 1985. PNC has designed and constructed the CPF at Tokai Works to conduct basic research on the reprocessing of FBR fuels. The Recycle Equipment Test Facility, an engineering scale hot facility, is now being designed for further R and D in this field. It will start hot operation in the mid-1990s.

• OSTI ID: 6393306
• Report Number(s): CONF-891103--
• Journal Information: Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
BREEDER REACTORS
BURNUP
CONSTRUCTION
DESIGN
DISSOLUTION
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FUEL CYCLE
FUEL ELEMENTS
FUEL REPROCESSING PLANTS
FUELS
HEAVY WATER MODERATED REACTORS
HWLWR TYPE REACTORS
JATR REACTOR
MIXED OXIDE FUELS
NATURAL URANIUM REACTORS
NUCLEAR FACILITIES
PLUTONIUM REACTORS
PLUTONIUM RECYCLE
POWER REACTORS
REACTOR COMPONENTS
REACTORS
REPROCESSING
RESEARCH PROGRAMS
SEPARATION PROCESSES
SOLID FUELS
TEST FACILITIES
THERMAL REACTORS
TIME DEPENDENCE
WATER COOLED REACTORS