Preliminary thermal-hydraulic design and predicted performance of the Clinch River Breeder Reactor core
The preliminary thermofluids design of the core assemblies of the Clinch River Breeder Reactor Plant (CRBRP) is presented along with the predicted performance for various plant operating conditions. The selected radial blanket assemblies shuffling scheme and the new approach adopted for fuel and blanket assemblies orificing is discussed. Relevant thermofluids parameters (assembly flow rate and mixed mean outlet temperature, fuel rod temperatures, fission gas plenum pressure, etc.) are presented. Highlights of a detailed uncertainties study performed are summarized. This preliminary analysis has shown that the CRBRP core behavior is compatible with design limits and requirements; future developments for a final analysis are outlined. (auth)
- Research Organization:
- Westinghouse Electric Corp., Madison, Pa. (USA). Advanced Reactors Div.
- DOE Contract Number:
- AT(11-1)-2395
- NSA Number:
- NSA-33-006729
- OSTI ID:
- 4159482
- Report Number(s):
- CONF-750804-11
- Resource Relation:
- Conference: Conference on heat transfer, San Francisco, California, USA, 11 Aug 1975; Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of oxide- and metal-core behavior during CRBRP (Clinch River Breeder Reactor Plant) station blackout
Role and progress of the Clinch River Breeder Reactor Plant