Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX

Journal Article · Fri Oct 15 04:00:00 EDT 2004 · Nuclear Science and Engineering

OSTI ID:20808390

Langenbuch, S; Schmidt, K -D; Velkov, K ^[1]

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

The OECD/NRC boiling water reactor (BWR) turbine trip benchmark has been calculated by the coupled thermal-hydraulic neutronics system code ATHLET-QUABOX/CUBBOX developed by Gesellschaft fuer Anlagen- und Reaktorsicherheit. The results obtained for all three exercises and for the additional four hypothetical cases are presented. The physical phenomena determining the BWR pressure transient are studied and explained. The sensitivity of results to variations of the initial steady-state conditions and of parameters of the two-phase flow model is discussed. A comparison is also performed for exercise 2 between the reactor core model with 33 thermal-hydraulic channels (THCs) as specified and a reactor core model with 764 THCs using a 1:1 mapping scheme.

• OSTI ID: 20808390
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 2 Vol. 148; ISSN NSENAO; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
BWR TYPE REACTORS
COMPUTER CODES
GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT
MAPPING
REACTOR CORES
SENSITIVITY
STEADY-STATE CONDITIONS
THERMAL HYDRAULICS
TRANSIENTS
TURBINES
TWO-PHASE FLOW
VARIATIONS