Assessment of RELAP5/MOD3.1 using loft L2-2, L2-3, L2-5, LP-02-6, and LP-LB-1
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:427068
- Korea Advanced Energy Research Inst., Taejon (Korea, Republic of)
The capability of RELAP5/MOD3.1 to predict overall loss-of-coolant-accident (LOCA) thermal-hydraulic phenomena was assessed using loss-of-fluid test (LOFT) large-break loss-of-coolant experiment data. Considering the five large-break LOCA experiments of L2-2, L2-3, L2-5, LP-02-6, and LP-LB-1, code uncertainty with respect to peak cladding temperature (PCT) was quantified in terms of mean discrepancy and standard deviation as in the previous studies.
- OSTI ID:
- 427068
- Report Number(s):
- CONF-961103--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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