Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON
スポンサーリンク
概要
- 論文の詳細を見る
IMPACT is a complex software system under development at the Nuclear Power Engineering Corporation, that includes the severe accident analysis code (SAMPSON). SAMPSON is an integration of twelve modules and will be capable of simulating hypothesized severe accidents in a nuclear power plant in the final phase of the IMPACT project. As one of these modules, the Molten Core Relocation Analysis (MCRA) module simulates the relocation behavior of a molten core during a severe accident. MCRA adopts a multi-phase, multi-component, multi-velocity field model to simulate severe accident phenomena mechanistically. Herein, we describe flow regimes, interfacial area modeling and physics models such as the momentum exchange and phase change models. Two separate effect analyses are presented as verification of MCRA’s models following the model descriptions. First, the fluid dynamics of the multi-velocity field model was verified in the calculation of nitrogen gas bubbling through water in Leung’s experiment. Second, data of the JRC-Ispra KROTOS-37 experiment were adopted for verification of the multi-velocity field model and vaporization/condensation model. Calculation results of both analyses compared well with the experimental data. Finally, MCRA’s integrated function involving the melting/freezing model was demonstrated by calculating two-phase flow with a fuel rod and molten fuel.
- 社団法人 日本原子力学会の論文
- 2000-03-25
著者
-
Nakahara Katsuhiko
Toshiba Corporation
-
Shirakawa N
Power & Industrial Systems Reserch & Development Center Toshiba Corporation
-
Shirakawa Noriyuki
Toshiba Power & Industrial Systems R&d Center
-
Shirakawa Noriyuki
Institute Of Environmental Systems Faculty Of Engineering Kyushu University
-
Shirakawa Noriyuki
Nuclear Engineering Laboratory Toshiba Corporation
-
SATOH Nobuhide
Nuclear Power Engineering Corporation (NUPEC)
-
UJITA Hiroshi
Nuclear Power Engineering Corporation (NUPEC)
-
MIYAGI Kazumi
Nuclear Engineering Laboratory, Toshiba Corporation
-
HORIE Hideki
Nuclear Engineering Laboratory, Toshiba Corporation
-
NAKAHARA Katsuhiko
Nuclear Engineering Laboratory, Toshiba Corporation
-
SASAKAWA Hiroshi
Nuclear Engineering Laboratory, Toshiba Corporation
-
Horie H
Toshiba Power & Industrial Systems R&d Center
-
Horie Hideki
Power & Industrial Systems Reserch & Development Center Toshiba Corporation
-
Ujita H
Nuclear Power Engineering Corp. Tokyo
-
Miyagi Kazumi
Nuclear Engineering Laboratory Toshiba Corporation
-
Sasakawa Hiroshi
Nuclear Engineering Laboratory Toshiba Corporation
-
NAKAHARA Katsuhiko
Nuclear Engineering Laboratory, Toshiba Corp.
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
- Analysis of Core Degradation and Fission Products Release in Phebus FPT1 Test at IRSN by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON
- Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)
- Model Verification of the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON'
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON
- Laser Power Balance for Effective Multi-Step Photoionization of Degenerate Atoms.