Development of Severe Accident Analysis Code SAMPSON in IMPACT Project
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概要
- 論文の詳細を見る
IMPACT is the name of a program and of specific simulation software, which will perform full-scope and detailed calcutations of various phenomena in a nuclear power plant for a wide range of event scenarios. The four years of the IMPACT project Phase I have been completed, and each analysis module of the prototype version of the severe accident analysis code SAMPSON has been developed and verified by comparison with separate-effect test data. Verification of the integrated code with combinations of up to 11 analysis modules has been conducted, with the Analysis Control Module, to demonstrate the code capability and integrity. A 10-inch cold leg failure Loss of Coolant Accident in the Surry Plant was the assumed initiating event. The system analysis was divided into two cases; one was an in-vessel retention analysis when gap cooling was effective, the other was an analysis of phenomena when the event was extended to ex-vessel due to the reactor pressure vessel failure when gap cooling was not sufficient. Using the Analysis Control Module to select and execute adequate combinations of the various analysis modules dynamically according to the progression of plant phenomena and to control parallel processing, the goal of integrated calculations by SAMPSON with multiple analysis modules executing in parallel was achieved.
- 社団法人 日本原子力学会の論文
- 1999-11-25
著者
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Shirakawa N
Power & Industrial Systems Reserch & Development Center Toshiba Corporation
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Shirakawa Noriyuki
Toshiba Power & Industrial Systems R&d Center
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Shirakawa Noriyuki
Institute Of Environmental Systems Faculty Of Engineering Kyushu University
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Shirakawa Noriyuki
Nuclear Engineering Laboratory Toshiba Corporation
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Yamagishi Makoto
Reactor Safety Engineering Department, Mitsubishi Heavy Industries, Ltd.
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SATOH Nobuhide
Nuclear Power Engineering Corporation (NUPEC)
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UJITA Hiroshi
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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SATOH Nobuhide
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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NAITOH Masanori
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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HIDAKA Masataka
Power & Industrial Systems R&D Laboratory, Hitachi, Ltd.
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Naitoh Masanori
Advanced Simulation Systems Department Nuclear Power Engineering Corporation
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Ujita H
Nuclear Power Engineering Corp. Tokyo
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Ujita Hiroshi
Advanced Simulation Systems Department Nuclear Power Engineering Corporation
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Yamagishi Makoto
Reactor Control & Safety Engineering Department Mitsubishi Heavy Industries Ltd.
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Hidaka Masataka
Power & Industrial Systems R&d Laboratory Hitachi Ltd.
関連論文
- Analysis of the Void Distribution in a Circular Tube with the Two-Fluid Particle Interaction Method
- Simulation of the Rayleigh-Taylor Instability with the MPS Method
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON
- Analysis of Subcooled Boiling with the Two-Fluid Particle Interaction Method
- ICONE11-36423 Analysis of Fission Product Behaviors in the Phebus-FPT1 Test with IMPACT/SAMPSON Code
- ICONE11-36297 ANALYSIS OF THE THERMAL HYDRAULICS AND CORE DEGRADATION BEHAVIOR IN THE PHEBUS-FPT1 TEST TRAIN WITH IMPACT/SAMPSON CODE
- Analysis of Flows around a BWR Spacer by the Two-Fluid Particle Interaction Method
- Analysis of Jet Flows with the Two-Fluid Particle Interaction Method
- Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON
- Development of Severe Accident Analysis Code SAMPSON in IMPACT Project
- Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles,(I) Models and Verifications for Boiling Water Reactor Application
- Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)
- Development of Debris Coolability Analysis Module in Severe Accident Analysis Code SAMPSON for IMPACT Project
- Model Verification of the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON'
- Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON', (I)
- Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON', (II)
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON