RELAP5/MOD3.2 Analysis of a VVER-1000 Reactor with UO{sub 2} Fuel and Mixed-Oxide Fuel

Journal Article · Wed Dec 15 04:00:00 EST 2004 · Nuclear Technology

OSTI ID:20837907

Hassan, Yassin A; Chun, Fu ^[1]

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1. Texas A and M University (United States)

A RELAP5/MOD3.2 model of the VVER-1000/MODEL V320 nuclear power plant was modified and a large-break loss-of-coolant accident (LBLOCA) in the cold leg was simulated. In this analysis, the core consisted of 162 UO{sub 2} assemblies and 1 mixed-oxide assembly. The results from the simulation were compared with the results from a similar study performed with the Russian computer program TECH-M. An uncertainty analysis was performed on the peak cladding temperature following a similar methodology called code scaling, applicability, and uncertainty. Monte Carlo calculations were performed using the response surface inferred from 15 runs of RELAP5 calculations. The result of this study shows that the emergency core coolant system would be sufficient to keep the cladding temperature during the LBLOCA scenario well below the required maximum limit.

• OSTI ID: 20837907
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 3 Vol. 148; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLANTS
LOSS OF COOLANT
MIXED OXIDE FUELS
MONTE CARLO METHOD
NUCLEAR POWER PLANTS
URANIUM DIOXIDE
WWER TYPE REACTORS