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Development of components for the Gas-Cooled Fast Breeder Reactor program

Conference ·
The purpose of this paper is to present an overview of the principal component design differences, when compared with those of typical HTGRs, and the consequent influences on the GCFR component development programs. Development program plans are discussed and include those for the prestressed concrete reactor vessel (PCRV), the main helium circulator and its supporting systems, the steam generators, the reactor thermal shielding, and the fuel handling system. Facility requirements to support these development programs are also discussed. Studies to date show that GCFR component development continues to appear to be incremental in nature, and the required tests are adaptations of related HTGR test programs. (auth)
Research Organization:
General Atomic Co., San Diego, Calif. (USA)
DOE Contract Number:
E(04-3)-167
NSA Number:
NSA-33-004676
OSTI ID:
4171084
Report Number(s):
GA-A--13653; CONF-751007--5
Country of Publication:
United States
Language:
English