更新情報
第16回
3D-CFD&FEMを用いたPTS時のRPV構造健全性評価と保全最適化
著者:
阮 小勇,水田 航平,中筋 俊樹,森下 和功,(京都大)
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Finite Element Method Maintenance Pressurized Thermal Shock Reactor Pressure Vessel Three-dimensional Computational Fluid Dynamics
阮 小勇,水田 航平,中筋 俊樹,森下 和功,(京都大)
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Finite Element Method Maintenance Pressurized Thermal Shock Reactor Pressure Vessel Three-dimensional Computational Fluid Dynamics
The structural integrity of reactor pressure vessels (RPVs) is an important issue in the field of nuclear power plants. The RPV contains a reactor core, which is impossible to substitute. The pressurized thermal shock (PTS) loading is a critical issue in assessing the safety of RPV. The most severe situation takes places during cold water injection in the cold legs when the emergency core cooling system (ECCS) is operated due to LOCA. Under these circumstances, the PTS loading may lead the RPV to brittle fr...
英字タイトル:
3D-CFD and FEM Based Deterministic PTS Analysis for Optimizing RPV Maintenance Strategy
英字タイトル:
3D-CFD and FEM Based Deterministic PTS Analysis for Optimizing RPV Maintenance Strategy
第16回
AIを活用した圧力容器鋼中性子照射脆化予測の高度化
著者:
中筋 俊樹,森下 和功,(京都大)
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AI Irradiation Embrittlement Multiscale Modeling RPV steels
中筋 俊樹,森下 和功,(京都大)
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AI Irradiation Embrittlement Multiscale Modeling RPV steels
In order to keep nuclear safety, management of irradiation embrittlement of LWR pressure vessel steels is the one of important issues. In this study, we focus on the prediction of irradiation embrittlement. Conventionally, irradiation embrittlement prediction is performed by a numerical model based on the mechanism. In recent years, research in fields such as AI and Bayesian statistics has rapidly progressed. Therefore, in this study, in order to advance the irradiation embrittlement prediction, the irradia...
英字タイトル:
Modeling for Prediction of Irradiation Embrittlement of RPV steels using AI
英字タイトル:
Modeling for Prediction of Irradiation Embrittlement of RPV steels using AI
第16回
ベイズを用いた圧力容器鋼の照射脆化予測の検討 ー予測精度のより一層の向上に向けてー
著者:
森下 和功,中筋 俊樹,(京都大)
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Bayesian Estimation JEAC4201 Embrittlement Correlation Neutron Irradiation Embrittlement Reactor Integrity Reactor Pressure Vessel Statistics
森下 和功,中筋 俊樹,(京都大)
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Bayesian Estimation JEAC4201 Embrittlement Correlation Neutron Irradiation Embrittlement Reactor Integrity Reactor Pressure Vessel Statistics
An embrittlement correlation method is one of the most important techniques to ensure the integrity of pressure vessel steels in nuclear power plants. In Japan, this is being addressed in accordance with the Japan Electric Association Code (JEAC4201) that was constructed using actual measured data of irradiation embrittlement of pressure vessel steels. In the present study, as a key step towards developing more reliable methodologies, statistical arguments were made on the embrittlement data. Based on this,...
英字タイトル:
Application of Bayesian Estimation Method to Irradiation Embrittlement Correlation of RPV Steels
英字タイトル:
Application of Bayesian Estimation Method to Irradiation Embrittlement Correlation of RPV Steels
第14回
リスクを活用した合理的な圧力容器保全のための研究
著者:
中筋 俊樹,Toshiki NAKASUJI,阮 小勇,Xiaoyong RUAN,森下 和功,Kazunori MORISHITA
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Bayesian statistics Irradiation Embrittlement Reactor Pressure Vessel Risk Assessment
中筋 俊樹,Toshiki NAKASUJI,阮 小勇,Xiaoyong RUAN,森下 和功,Kazunori MORISHITA
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Bayesian statistics Irradiation Embrittlement Reactor Pressure Vessel Risk Assessment
Reactor pressure vessel (RPV) steels are subjected to neutron irradiation that can lead to loss of fracture toughness. One of the critical issues for RPV structural integrity is related to the pressurized thermal shock (PTS) event. Risk assessment is important for safety evaluation and maintenance planning of a nuclear power plant. In this study, a new method was developed to assess a failure risk of RPV at PTS event for the risk-based maintenance. The failure risk was caused by fluctuations of stress...
英字タイトル:
Risk-based Optimization of Reactor Pressure Vessel Maintenance
英字タイトル:
Risk-based Optimization of Reactor Pressure Vessel Maintenance
第14回
保全の視点に立脚した原子炉圧力容器の確率論的健全性評価
著者:
阮 小勇,Xiaoyong RUAN,中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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Computational Fluid Dynamics Finite Element Method Pressurized Thermal Shocks Probabilistic Integrity Evaluation Reactor Pressure Vessel
阮 小勇,Xiaoyong RUAN,中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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Computational Fluid Dynamics Finite Element Method Pressurized Thermal Shocks Probabilistic Integrity Evaluation Reactor Pressure Vessel
The structural integrity of a reactor pressure vessel (RPV) is important part of nuclear power plant safety. Pressurized thermal shock (PTS) takes place when the emergency core cooling system (ECCS) is operated and the coolant water is injected into the RPV due to a loss-of-coolant accident (LOCA). With the neutron irradiation, PTS loading may lead a RPV to fracture. In the present study, optimization of RPV maintenance is considered, where two different attempts are made to investigate the RPV integri...
英字タイトル:
From the Viewpoint of Maintenance, the Probabilistic Integrity Evaluation of Reactor Pressure Vessel
英字タイトル:
From the Viewpoint of Maintenance, the Probabilistic Integrity Evaluation of Reactor Pressure Vessel
第13回
加圧熱衝撃事象における圧力容器内き裂の応力拡大係数の3D-CFD&FEM解析
著者:
中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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Computational Fluid Dynamics Fracture Mechanics Pressurized Thermal Shocks Reactor Pressure Vessel Stress Intensity Factor
中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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Computational Fluid Dynamics Fracture Mechanics Pressurized Thermal Shocks Reactor Pressure Vessel Stress Intensity Factor
The integrity of the Reactor Pressure Vessel (RPV) subjected to Pressurized Thermal Shocks (PTS) by cold water injection through the cold leg owing to a Loss-Of-Coolant Accident (LOCA). Fracture Mechanics (FM) analysis evaluation for cracks of the inner surface in the RPV during PTS events, which is important in assessing the safety of nuclear power plants. Conventional, one-dimensional thermal hydraulic analysis and simple model fracture mechanics analysis has been performed. In the present study, the...
英字タイトル:
3D-CFD & FEM analysis of RPV stress intensity factor for cracks subjected to PTS phenomena 京都大学 阮 小勇 Xiaoyong RUAN Member
英字タイトル:
3D-CFD & FEM analysis of RPV stress intensity factor for cracks subjected to PTS phenomena 京都大学 阮 小勇 Xiaoyong RUAN Member
第12回
原子炉圧力容器の保全活動高度化に関する研究
著者:
中筋 俊樹,Toshiki NAKASUJI,山本 泰功,Yasunori YAMAMOTO,阮 小勇,Xiaoyong RUAN,森下 和功,Kazunori MORISHITA
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Fuel cladding Numerical simulation PRA Reactor pressure vessel Risk-based maintenance
中筋 俊樹,Toshiki NAKASUJI,山本 泰功,Yasunori YAMAMOTO,阮 小勇,Xiaoyong RUAN,森下 和功,Kazunori MORISHITA
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公開日:
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Fuel cladding Numerical simulation PRA Reactor pressure vessel Risk-based maintenance
In Japan, the government decided that nuclear power was used as one of the energy sources for base load energy. Nuclear power plants are required more safety. The plant safety have kept since the start of operation due to the maintenance. Since the maintenance plan should be continued improving, there is still issues for improvement in the plan. In this study, we systematize the methods of the plant maintenance. We review the maintenance plan of reactor pressure vessel and fuel cladding tube and indic...
英字タイトル:
Advanced maintenance methodology was developed for the keeping integrity of reactor pressure vessel
英字タイトル:
Advanced maintenance methodology was developed for the keeping integrity of reactor pressure vessel
第15回
圧力容器の健全性評価に関する研究 ?照射脆化予測のあいまいさの一考察?
著者:
中筋 俊樹, 森下 和功,(京都大)
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Irradiation embrittlement Modeling Prediction RPV
中筋 俊樹, 森下 和功,(京都大)
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Irradiation embrittlement Modeling Prediction RPV
The reactor pressure vessel (RPV) has the function as the reactor coolant pressure boundary (RCPB) which is damaged by neutron irradiation embrittlement. In order to keep the function, maintenance activities should be done to manage irradiation embrittlement. In this study, we investigated the precision of the prediction model of irradiation embrittlement applied by Japan’s nuclear regulation. Finally, we discussed the precision required for adequate management.
...
英字タイトル:
Integrity Assessment of Reactor Pressure Vessel Steel: Ambiguity of Predicting Irradiation Embrittlement
英字タイトル:
Integrity Assessment of Reactor Pressure Vessel Steel: Ambiguity of Predicting Irradiation Embrittlement
第13回
圧力容器鋼の照射脆化に伴うリスクの低減に向けて :材料シミュレーションからのアプローチ
著者:
中筋 俊樹,Toshiki NAKASUJI,阮 小勇,Xiaoyoug RUAN,森下 和功,Kazunori MORISHITA
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公開日:
キーワードタグ:
Irradiation Embrittlement Reactor Pressure Vessel Risk Assessment
中筋 俊樹,Toshiki NAKASUJI,阮 小勇,Xiaoyoug RUAN,森下 和功,Kazunori MORISHITA
発刊日:
公開日:
キーワードタグ:
Irradiation Embrittlement Reactor Pressure Vessel Risk Assessment
Reactor pressure vessel (RPV) steels are subjected to neutron irradiation that can lead to loss of fracture toughness. One of the critical issues for RPV structural integrity is related to the pressurized thermal shock (PTS) event. Risk assessment is important for safety evaluation and maintenance planning of a nuclear power plant. In this study, a risk assessment method of failure of reactor pressure vessel at PTS event was developed for the risk- based maintenance. The failure risk was caused by fluctua...
英字タイトル:
Reduce the risks associated with irradiation embrittlement of RPV steels: Approach from simulation of microstructural change in steels during irradiation
英字タイトル:
Reduce the risks associated with irradiation embrittlement of RPV steels: Approach from simulation of microstructural change in steels during irradiation
第10回
最適な原子炉保全のための燃料リークに起因するリスク評価
著者:
山本 泰功,Yasunori YAMAMOTO,中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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fuel cladding fuel failure fuel leak Monte Carlo method risk assessment
山本 泰功,Yasunori YAMAMOTO,中筋 俊樹,Toshiki NAKASUJI,森下 和功,Kazunori MORISHITA
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公開日:
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fuel cladding fuel failure fuel leak Monte Carlo method risk assessment
Continuous efforts should be made to keep the safety of light-water reactors, not only at the design and construction phases but also at the operation phase. Fuel cladding is a key barrier in containing fission product. However, fuel failures yet occur in operating nuclear power plants, often leading to reactor shutdown based on the conservative, sometimes too conservative, judgment. Therefore, an appropriate judgment of how to treat the fuel failure is required to achieve reasonable management of reac...
英字タイトル:
Risk assessment of reactor shut-down due to fuel failure for sufficient management of nuclear reactors
英字タイトル:
Risk assessment of reactor shut-down due to fuel failure for sufficient management of nuclear reactors