Three-dimensional time-dependent STAR reactor kinetics analyses coupled with RETRAN and MCPWR system response
- New York Power Authority, White Plains (USA)
The operation of a nuclear power plant must be regularly supported by various reactor dynamics and thermal-hydraulic analyses, which may include final safety analysis report (FSAR) design-basis calculations, and conservative and best-estimate analyses. The development and improvement of computer codes and analysis methodologies provide many advantages, including the ability to evaluate the effect of modeling simplifications and assumptions made in previous reactor kinetics and thermal-hydraulic calculations. This paper describes the results of using the RETRAN, MCPWR, and STAR codes in a tandem, predictive-corrective manner for three pressurized water reactor (PWR) transients: (a) loss of feedwater (LOF) anticipated transient without scram (ATWS), (b) station blackout ATWS, and (c) loss of total reactor coolant system (RCS) flow with a scram.
- OSTI ID:
- 5487499
- Report Number(s):
- CONF-891103--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 60; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BENCHMARKS
BLACKOUTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
KINETICS
LOSS OF COOLANT
M CODES
MECHANICS
OPERATION
OXYGEN COMPOUNDS
POWER DISTRIBUTION
PRESSURIZATION
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
S CODES
SAFETY
SCRAM
SECONDARY COOLANT CIRCUITS
SHUTDOWN
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS