The ANF (Advanced Nuclear Fuels Corporation)-RELAP small-break LOCA (loss-of-coolant accident) analysis for the Comanche Peak steam electric station

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

OSTI ID:6340279

Chu, C C; Choe, W G ^[1]

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1. Texas Utilities Electric, Dallas (USA)

The system response code RELAP/MOD2 Idaho National Engineering Laboratory cycle 36.02, with modifications developed by Advanced Nuclear Fuels Corporation (ANF), was used to perform small-break loss-of-coolant accident (SBLOCA) calculations for the Comanche Peak steam electric station (CPSES) unit 1. The ability of the ANF-RELAP code to calculate the SBLOCA system response for the four-loop pressurized water reactor is presented by discussing the overall system response, the system mass distribution, and the core response.

• OSTI ID: 6340279
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-004419
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (USA), 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
42 ENGINEERING
COMANCHE PEAK-1 REACTOR
REACTOR SAFETY
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
DEPRESSURIZATION
IDAHO NATIONAL ENGINEERING LABORATORY
PIPES
PLUGGING
PRESSURIZATION
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR CORES
REACTOR KINETICS
RUPTURES
STEAM GENERATORS
TWO-PHASE FLOW
ACCIDENTS
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID FLOW
FLUID MECHANICS
KINETICS
MECHANICS
NATIONAL ORGANIZATIONS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
US DOE
US ERDA
US ORGANIZATIONS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
420400 - Engineering- Heat Transfer & Fluid Flow