Civex nuclear fuel cycle examined by U. S. team. [Summary of AIF panel study]
Journal Article
·
· Public Util. Fortn.; (United States)
OSTI ID:6410933
A panel of industrial experts formed by the Atomic Industrial Forum (AIF) has examined the feasibility of the Civex nuclear fuel cycle and recommends further development as a possible deterrent to plutonium fuel proliferation. The AIF panel notes, however, that there are still some technical and economic questions to be answered. Intended for civilian use, the Civex process developers wanted a system that would discourage the diversion of plutonium for weapons use by keeping each step of the fuel cycle highly radioactive. Based on the Purex fuel processing method, Civex plants will be more costly to build but operating expenses will be comparable. The panel also concluded that the potential advantages warrant the necessary 20-year research investment. (DCK)
- OSTI ID:
- 6410933
- Journal Information:
- Public Util. Fortn.; (United States), Journal Name: Public Util. Fortn.; (United States) Vol. 102:10; ISSN PUFNA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210800 -- Nuclear Power Plants-- Economics
29 ENERGY PLANNING, POLICY, AND ECONOMY
290600* -- Energy Planning & Policy-- Nuclear Energy
ACTINIDES
CIVEX PROCESS
DEPLETED URANIUM
ELEMENTS
EVALUATION
FUEL CYCLE
MANAGEMENT
METALS
NUCLEAR MATERIALS DIVERSION
NUCLEAR MATERIALS MANAGEMENT
PROLIFERATION
REPROCESSING
SAFETY
SEPARATION PROCESSES
URANIUM
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210800 -- Nuclear Power Plants-- Economics
29 ENERGY PLANNING, POLICY, AND ECONOMY
290600* -- Energy Planning & Policy-- Nuclear Energy
ACTINIDES
CIVEX PROCESS
DEPLETED URANIUM
ELEMENTS
EVALUATION
FUEL CYCLE
MANAGEMENT
METALS
NUCLEAR MATERIALS DIVERSION
NUCLEAR MATERIALS MANAGEMENT
PROLIFERATION
REPROCESSING
SAFETY
SEPARATION PROCESSES
URANIUM