Summary of the First Workshop on OECD/NRC boiling water reactor turbine trip benchmark
Description
The reference problem chosen for simulation in a BWR is a Turbine Trip transient, which begins with a sudden Turbine Stop Valve (TSV) closure. The pressure oscillation generated in the main steam piping propagates with relatively little attenuation into the reactor core. The induced core pressure oscillation results in dramatic changes of the core void distribution and fluid flow. The magnitude of the neutron flux transient taking place in the BWR core is strongly affected by the initial rate of pressure rise caused by pressure oscillation and has a strong spatial variation. The correct simulation of the power response to the pressure pulse and subsequent void collapse requires a 3-D core modeling supplemented by 1-D simulation of the remainder of the reactor coolant system. A BWR TT benchmark exercise, based on a well-defined problem with complete set of input specifications and reference experimental data, has been proposed for qualification of the coupled 3-D neutron kinetics/thermal-hydraulic system transient codes. Since this kind of transient is a dynamically complex event with reactor variables changing very rapidly, it constitutes a good benchmark problem to test the coupled codes on both levels: neutronics/thermal-hydraulic coupling and core/plant system coupling. Subsequently, the objectives of the proposed benchmark are: comprehensive feedback testing and examination of the capability of coupled codes to analyze complex transients with coupled core/plant interactions by comparison with actual experimental data. The benchmark consists of three separate exercises: Exercise 1 - Power vs. Time Plant System Simulation with Fixed Axial Power Profile Table (Obtained from Experimental Data). Exercise 2 - Coupled 3-D Kinetics/Core Thermal-Hydraulic BC Model and/or 1-D Kinetics Plant System Simulation. Exercise 3 - Best-Estimate Coupled 3-D Core/Thermal-Hydraulic System Modeling. This first workshop was focused on technical issues connected with the first draft of the Benchmark Specifications and the definition of three exercises. The information needed for the exercises was clearly presented to the participants in order to be able to proceed with the calculations in an efficient and timely manner. Three workshops are scheduled during the course of the benchmark activities. This document is the summary of the First Workshop
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- NEA-NSC-DOC--2000-22
Conference
- Title
- 1. Workshop on OECD/NRC boiling water reactor turbine trip benchmark
- Dates
- 9-10 Nov 2000
- Place
- Philadelphia (United States)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 48099105
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; BENCHMARKS; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; FLOW MODELS; NEUTRON FLUX; OSCILLATIONS; PRESSURE DEPENDENCE; REACTOR CORES; SPATIAL DISTRIBUTION; THERMAL HYDRAULICS; TRANSIENTS; VOIDS
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENRICHED URANIUM REACTORS; EVALUATION; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; POWER REACTORS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS