Analysis of coolability of the control rods of a Savannah River Site production reactor with loss of normal forced convection cooling
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Science Applications International Corp., Albuquerque, NM (United States)
An analytical study of the coolability of the control rods in the Savannah River Site (SRS) K-Production Reactor under conditions of loss of normal forced convection cooling has been performed. The study was performed as part of the overall safety analysis of the reactor supporting its restart. The analysis addresses the buoyancy-driven flow over the control rods that occurs when forced cooling is lost, and the limit of critical heat flux that sets the acceptance criteria for the study. The objective of the study is to demonstrate that the control rods will remain cooled at powers representative of those anticipated for restart of the reactor. The study accomplishes this objective with a very tractable simplified analysis for the modest restart power. In addition, a best-estimate calculation is performed, and the results are compared to results from sub-scale scoping experiments. 5 refs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10142314
- Report Number(s):
- WSRC-MS-92-129; CONF-920903-5; ON: DE92013219
- Resource Relation:
- Conference: International topical meeting on reactor thermal hydraulics: towards the next generation of nuclear power plants,Salt Lake City, UT (United States),20-24 Sep 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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