Published June 1987
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Calculation of MCPR [minimum critical power ratio] for BWR transients using the BNL plant analyzer
Description
The critical power ratio (CPR) is used for determining the thermal limits of boiling water reactors. In this study, critical power ratios for a series of transients run on the Brookhaven Plant Analyzer (BPA) [1] have been calculated. The transients include nominal base case simulations, simulations with variations in relief valve setpoints and the number of failed feedwater heaters, simulations at the 100% power, 75% flow point on the extended load line of the MEOD, and a simulation with partial feedwater heating. The plant represented with the BPA is a BWR/4 rated at 3293 MW with a 6.38 m (251'') vessel. Data were obtained by the Plant Analyzer Development Group at BNL from a variety of sources describing the Browns Ferry Plant
Availability note (English)
Available from NTIS, PC A02/MF A01 as DE87012109.Files
19023473.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- BNL-NUREG--39959
Conference
- Title
- Joint meeting of the American Nuclear Society and the Atomic Industrial Forum.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FAILURES; FEEDWATER; HEATING; REACTOR COMPONENTS; REACTOR SAFETY; REACTOR SIMULATORS; THERMAL ANALYSIS; TRANSIENTS
- Descriptors DEC
- ANALOG SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTORS; SAFETY; SIMULATORS; SOLVENTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-871101--36.