Analysis of the behavior of the safety systems of the AP600 for small-break LOCAs

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:426486

Hassan, Y A; Banerjee, S ^[1]

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1. Texas A&M Univ., College Station, TX (United States)

The Westinghouse advanced passive 600-MW(electric) (AP600) reactor is undergoing design certification by the U.S. Nuclear Regulatory Commission. As a part of this certification, the response of the AP600 safety systems to a spectrum of small cold-leg breaks was studied using RELAP5/MOD3.2. The AP600 is one of the next generation of light water reactors. It is a pressurized water reactor with a low core power density to increase the margin for safety.

• OSTI ID: 426486
• Report Number(s): CONF-961103--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTERIZED SIMULATION
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
R CODES