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

• Published in: Nuclear science and engineering Vol. 148; no. 2; pp. 270 - 280
• Main Authors: Langenbuch, S., Schmidt, K.-D., Velkov, K.
• Format: Journal Article
• Language: English
• Published: La Grange Park, IL Taylor & Francis 01.10.2004; American Nuclear Society
• Subjects: Applied sciences; BENCHMARKS; BWR TYPE REACTORS; COMPUTER CODES; Energy; Energy. Thermal use of fuels; Engines and turbines; Equipments for energy generation and conversion: thermal, electrical, mechanical energy, etc; Exact sciences and technology; Fission nuclear power plants; Fuels; GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT; Installations for energy generation and conversion: thermal and electrical energy; MAPPING; Nuclear fuels; REACTOR CORES; SENSITIVITY; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TRANSIENTS; TURBINES; TWO-PHASE FLOW; VARIATIONS; Two phase flow; Unsteady state; Turbine; Computation code; Modeling; Steady state; Transients; Nuclear reactor; Boiling water reactor; Benchmark calculation; Thermohydraulics; Thermal reactor; Comparative study; Reactor core
• ISSN: 0029-5639; 1943-748X
• DOI: 10.13182/NSE04-A2457

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 für 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.