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AbstractAbstract
[en] Over the past several years, much has been accomplished in the joint US government-industry GCFR program. Some highlights are as follows: The conceptual design of the Nuclear Steam Supply system for a 350 MW(e) demonstration plant was completed. The design features an upflow core, a multi-cavity Prestressed Concrete Reactor Vessel, electric motor drivers for the main helium circulators, and significantly greater provision for residual heat removal than in prior designs. Development plans were completed and costed for all major components and systems. At Oak Ridge National Laboratory, the basic Core Flow Test Loop has been completed. This is a heat transfer and fluid flow facility with capability to cool with helium a bundle of 91 electrically-heated fuel rods operating at maximum GCFR linear heat rates under steady state, transient and accident conditions. It is being converted for use on the High Temperature Gas-Cooled Reactor Program. The F-5 subassembly of GCFR fuel rods continues to be irradiated in the Experimental Breeder Reactor-2 under the auspices of Argonne National Laboratory. A series of critical assembly tests were carried out at Argonne National Laboratory. Experiments have also been done using the Tower Shielding Facility at Oak Ridge National Laboratory to determine the extent of neutron streaming from the core. All the design and development work which has been done to date, both in the United States and in Europe, has given positive results
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 418 p; Mar 1983; p. 59-71; Technical committee on gas-cooled reactors; Minsk (Byelorussian SSR); 12-16 Oct 1981
Record Type
Report
Literature Type
Conference
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Reference NumberReference Number
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