Three-dimensional time-dependent STAR reactor kinetics analyses coupled with RETRAN and MCPWR system response

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5487499

Feltus, M A ^[1]

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1. 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-; CODEN: TANSA; TRN: 91-024640
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR SAFETY
REACTOR ACCIDENTS
M CODES
R CODES
S CODES
ATWS
BENCHMARKS
BLACKOUTS
FEEDWATER
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
POWER DISTRIBUTION
PRESSURIZATION
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
SCRAM
SECONDARY COOLANT CIRCUITS
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN COMPOUNDS
KINETICS
MECHANICS
OPERATION
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWN
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled