Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the Coupled Code System ATHLET-QUABOX/CUBBOX

Journal Article · Thu May 15 04:00:00 EDT 2003 · Nuclear Technology

OSTI ID:20826847

Langenbuch, Siegfried; Schmidt, Klaus-Dieter; Velkov, Kiril ^[1]

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1. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH (France)

The Organization for Economic Cooperation and Development (OECD) Pressurized Water Reactor Main Steam Line Break (MSLB) Benchmark has been calculated for all three exercises by the coupled code system ATHLET-QUABOX/CUBBOX developed by Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The results obtained are presented, and a detailed comparison with other solutions of the benchmark is discussed. An attempt is made to explain the differences observed in the solutions by the different modeling of physical processes in the codes. The sensitivity of results on modeling features is also investigated. In addition, the effect of different mapping schemes between fuel assemblies of the core loading and the thermal-fluid dynamics on the accuracy of three-dimensional (3-D) neutronics solutions is studied. The results for the MSLB transient are also evaluated to compare 3-D neutronics and point-kinetics solutions in view of integral and local parameters. Thus, the experiences with the coupled code system ATHLET-QUABOX/CUBBOX during the MSLB benchmark activity are summarized.

• OSTI ID: 20826847
• 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
ACCURACY
BENCHMARKS
COMPARATIVE EVALUATIONS
FLUID MECHANICS
FUEL ASSEMBLIES
GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT
MAPPING
OECD
PWR TYPE REACTORS
SIMULATION
STEAM LINES
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS