Use of SCDAP/RELAP5 results in severe accident-induced tube rupture risk assessment

Journal Article · Mon Dec 01 04:00:00 EST 1997 · Transactions of the American Nuclear Society

OSTI ID:552620

Donoghue, J; Lee, R ^[1]

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1. Nuclear Regulatory Commission, Rockville, MD (United States)

This study was conducted to provide the basis for an estimate of the containment bypass risk presented by severe accident-induced steam generator tube rupture. During severe accidents, components can be heated to the extent that induced rupture might occur as a result of the combined effects of pressure and temperature. The potential for tube failure can be exacerbated by flaws in the tubes and by depressurization of the secondary system since pressure differential across the tubes is increased. SCDAP/RELAP5 analyses were performed to predict reactor coolant system (RCS) conditions during station black-out (SBO) sequences using a plant model for Surry. The steam generator tube creep rupture model in SCDAP/RELAP5 was not directly applicable to this assessment since it does not account for tube flaws. Therefore, a separate tube failure model was used to predict tube creep failure. This model used the same Larson-Miller approach applied in SCDAP/RELAP5 but is based on high-temperature tube burst experiments of flawed tubes. The results were then applied to determine tube failure probability and subsequent containment bypass potential resulting from severe accident conditions.

• OSTI ID: 552620
• Report Number(s): CONF-971125--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; 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
CONTAINMENT
DEPRESSURIZATION
HYDRAULICS
OUTAGES
PROBABILITY
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
S CODES
SURRY-2 REACTOR