CEA-IRSN Participation in the Main Steam Line Break Benchmark

Journal Article · Thu May 15 00:00:00 EDT 2003 · Nuclear Technology

OSTI ID:20826850

Royer, E ^[1]; Raimond, E ^[2]; Caruge, D ^[1]

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1. Commissariat a l'Energie Atomique (France)
2. Institut de Radioprotection et de Surete Nucleaire (France)

The Organization for Economic Cooperation and Development/Nuclear Energy Agency Main Steam Line Break (MSLB) benchmark provides a comparison of state-of-the-art and best-estimate models used to compute reactivity accidents. A comprehensive study has been carried out by Commissariat a l'Energie Atomique and Institut de Radioprotection et de Surete Nucleaire with the CATHARE, CRONOS2, and FLICA4 codes. The effect of mixing between primary loops in the core vessel is analyzed, then zero-dimensional and three-dimensional (3-D) kinetics are compared, and finally, the effect of the core thermal-hydraulic model is presented. The aim of this analysis is to assess the 3-D effects in the MSLB accident and to explain the return-to-power occurrence.

• OSTI ID: 20826850
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 2 Vol. 142; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
CEA
COMPARATIVE EVALUATIONS
CONTAINERS
KINETICS
MIXING
NEA
REACTIVITY
REACTOR ACCIDENTS
STEAM LINES
THERMAL HYDRAULICS
THREE-DIMENSIONAL CALCULATIONS