Present status of fast breeder reactor fuel cycle development at PNC

Journal Article · Wed Jan 31 23:00:00 EST 1990 · Nuclear Technology; (USA)

OSTI ID:6892941

Yamamoto, M ^[1]; Matsumoto, K -I ^[2]

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1. Power Reactor and Nuclear Fuel Development Corp., Nuclear Fuels Development Div., 9-13 Akasaka, Minato-ku, Tokyo (JP)
2. Power Reactor and Nuclear Fuel Development Corp., Reprocessing Development Div., 9-13 Akasaka, Minato-ku, Tokyo (JP)

This paper discusses the development of spent-fuel reprocessing technology and mixed-oxide (MOX) fuel conversion as they are indispensable to the establishment of the fast breeder reactor (FBR) fuel cycle. The authors describe various fabrication and conversion facilities and their capabilities.

• OSTI ID: 6892941
• Journal Information: Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 89:2; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

050700 -- Nuclear Fuels-- Fuels Production & Properties
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
29 ENERGY PLANNING, POLICY, AND ECONOMY
290500 -- Energy Planning & Policy-- Research
Development
Demonstration
& Commercialization
ACTINIDES
BREEDER REACTORS
COORDINATED RESEARCH PROGRAMS
DESIGN
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EUROPE
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FEDERAL REPUBLIC OF GERMANY
FUEL CYCLE
FUEL REPROCESSING PLANTS
FUELS
LIQUID METAL COOLED REACTORS
MATERIALS
METALS
MONJU REACTOR
NORTH AMERICA
NUCLEAR FACILITIES
NUCLEAR FUELS
PLUTONIUM
POWER REACTORS
REACTOR MATERIALS
REACTORS
RESEARCH PROGRAMS
SODIUM COOLED REACTORS
SPENT FUELS
TEST FACILITIES
TRANSURANIUM ELEMENTS
UNITED KINGDOM
URANIUM
USA
WESTERN EUROPE