Feasibility study on feed and bleed for pressurized-water reactors
Conference
·
OSTI ID:5624683
By injecting coolant with a high pressure emergency core cooling system, and removing the heated/vaporized fluid by way of the pressurizer power operated relief valve, primary feed and bleed cooling denotes an operation whereby reactor core cooling is maintained. This paper presents the results from an experimental and analytical study that includes a simplified analysis of mass and energy balances associated with the feed and bleed, examination of test data from the Semiscale system, RELAP5 code analyses of both Semiscale and a four-loop Westinghouse plant, and the primary coolant system behavior for a transient that leads to the need for feed and bleed. Examination of the parameters that govern a stable feed and bleed operation identifies four key parameters such as: (a) core decay heat, (b) cooling water injection capacity, (c) power operated relief valve (PORV) energy removal rate, and (d) PORV mass removal rate. A simplified analytical approach to determining if stable feed and bleed is feasible, has been developed and corroborated by experimental data and computer code calculations.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5624683
- Report Number(s):
- EGG-M-08683; CONF-830702-24; ON: DE84000564
- Country of Publication:
- United States
- Language:
- English
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