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