176件が見つかりました。
第17回
Numerical investigation of debris remelting in RPV lower head by a multiphase particle method
著者:
Guangtao Duan,酒井 幹夫 ,（東京大）
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Debris remelting Fluid-solid interaction Local hot spots MPS method Multi-time scale Phase change
Guangtao Duan,酒井 幹夫 ,（東京大）
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Debris remelting Fluid-solid interaction Local hot spots MPS method Multi-time scale Phase change
Debris remelting may play an important role in the progression analysis of severe accidents and the safety design of nuclear power plants. This paper developed a multiphase moving particle semi-implicit (MPS) method by coupling the fluid-solid interaction, solid-solid interaction, heat transfer and phase change models. Then, the debris remelting in reactor pressure vessel (RPV) is simulated, and the influence of debris size and decay heat power via local hot spots is investigated....
第17回
PD資格試験実施から15年の実施状況
著者:
渡辺 恵司,林 山,東海林 一,（電中研）
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Crack Depth sizing Performance Demonstration Ultrasonic Testing
渡辺 恵司,林 山,東海林 一,（電中研）
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Crack Depth sizing Performance Demonstration Ultrasonic Testing
The PD Center of Central Research Institute of Electric Power Industry (CRIEPI) commenced performance demonstration examinations (PD examination) for flaw depth sizing of austenitic stainless steel pipes in March 2006. At the end of FY 2020, 54 examination sessions had been completed and 72 candidates had passed the examination. The total number of PD examinee including re-examination and re-certification was 124. Passed candidates can perform depth sizing of SCC flaws with a high level of accuracy. As a re...
英字タイトル:
Current status of Japanese PD examination for 15 years
英字タイトル:
Current status of Japanese PD examination for 15 years
第17回
PWR1次冷却水環境下でのマグネタイト生成メカニズム等に 関する検討
著者:
井門 賢一,中川 和重,（四国電力）,山本 松平,（四国総研）,大鹿 浩功,（四国電力）
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corrosion drive shaft Ikata Unit3 magnetite primary coolant system SUS410
井門 賢一,中川 和重,（四国電力）,山本 松平,（四国総研）,大鹿 浩功,（四国電力）
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公開日:
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corrosion drive shaft Ikata Unit3 magnetite primary coolant system SUS410
Inadvertent withdrawal of a control rod cluster was observed during lifting of the upper core structure on the 15th outage of Ikata Unit3. The source of magnetite sludge, which is one of the causes of this event, was presumed to be the drive shaft, but there is little knowledge about the corrosion characteristics of the drive shaft material SUS410 in the PWR primary water.
Therefore, we investigated the corrosion characteristics of SUS410 in simulated PWR primary water circumstance at the plant start-up sta...
英字タイトル:
Investigation on magnetite formation mechanism in PWR primary coolant system environment
英字タイトル:
Investigation on magnetite formation mechanism in PWR primary coolant system environment
第17回
Radiation-Induced Volume Expansion in Concrete Aggregate Minerals Studied by Ion Irradiation and Step Height Measurement
著者:
Muammar Hawary Patris, Kenta Murakami, Luu Vu Nhut, Xinrun Chen,（長岡技科大）, Ippei Maruyama,（名古屋大）, Takahiro Ohkubo,（千葉大）, Kiyoteru Suzuki,（三菱総研）
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aggregate minerals amorphization Ion irradiation radiation-induced volume expansion
Muammar Hawary Patris, Kenta Murakami, Luu Vu Nhut, Xinrun Chen,（長岡技科大）, Ippei Maruyama,（名古屋大）, Takahiro Ohkubo,（千葉大）, Kiyoteru Suzuki,（三菱総研）
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aggregate minerals amorphization Ion irradiation radiation-induced volume expansion
Long-term radiation exposure can cause damage of concrete structures due to the volume expansion of the aggregate minerals. In this study, granite, sandstone, and tuff were irradiated with 2.8 MeV Fe2+ at room temperature to different level of ion fluences. Step height measurement was conducted to quantify the volume change. It was found that the swelling of all minerals saturated at around 300 nm. Tuff, which contains almost all silica, exhibited the fastest swelling, among others.
...
第17回
Reliability analysis of pipes suffering wall thinning based on extreme value analysis of ultrasonic thickness measurement
著者:
宋 海成,遊佐 訓孝,（東北大）
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Bayesian theorem extreme value analysis measurement uncertainty pipe wall thinning risk analysis ultrasonic testing
宋 海成,遊佐 訓孝,（東北大）
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Bayesian theorem extreme value analysis measurement uncertainty pipe wall thinning risk analysis ultrasonic testing
This study proposes to use extreme value analysis to characterize the uncertainty in estimating the wall thickness of carbon steel pipes by ultrasonic testing. The goodness of fit has been examined using experimental data measured from plate samples processed by corrosion test. A model is subsequently developed for predicting the failure probability of carbon steel pipes suffering wall thinning based on Bayesian theorem. In this model, the wall thinning rate predicted by KWU-KR model can be updated by offer...
英字タイトル:
Reliability analysis of pipes suffering wall thinning based on extreme value analysis of ultrasonic thickness measurement
英字タイトル:
Reliability analysis of pipes suffering wall thinning based on extreme value analysis of ultrasonic thickness measurement
第17回
RPV保全最適化のための3D-CFD＆FEMによるPTS時の 構造健全性評価：非対称原子炉冷却の効果
著者:
阮 小勇,（京都大,QST）,森下 和功,（京都大）
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Asymmetric Cooling Injection Finite Element Method Pressurized Thermal Shock Reactor Pressure Vessel Structural Integrity Assessment Three-Dimensional Computational Fluid Dynamics
阮 小勇,（京都大,QST）,森下 和功,（京都大）
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Asymmetric Cooling Injection Finite Element Method Pressurized Thermal Shock Reactor Pressure Vessel Structural Integrity Assessment Three-Dimensional Computational Fluid Dynamics
The structural integrity of a reactor pressure vessel (RPV) is significant for nuclear plant safety. In assessing the integrity of the RPV, one of the most severe situations to be considered is pressurized thermal shock (PTS) during emergency water cooling. Many efforts have been made to understand this PTS, and these efforts assumed symmetric reactor cooling injection. However, once extreme circumstances occur, such as a major earthquake, some of the cooling injections will fail. This failure makes symmetr...
英字タイトル:
Pressurized Thermal Shock Analysis of a Reactor Pressure Vessel for Optimizing the Maintenance Strategy: Effect of Asymmetric Reactor Cooling
英字タイトル:
Pressurized Thermal Shock Analysis of a Reactor Pressure Vessel for Optimizing the Maintenance Strategy: Effect of Asymmetric Reactor Cooling
第17回
WJPとバフ研磨による残留応力改善工法の 応力緩和挙動のメカニズム検討
著者:
于 麗娜,才田 一幸,西本 和俊,（大阪大）,千種 直樹,（関西電力）
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Buffing EBSD Hardness Positron lifetime WJP
于 麗娜,才田 一幸,西本 和俊,（大阪大）,千種 直樹,（関西電力）
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Buffing EBSD Hardness Positron lifetime WJP
The relaxation behavior of the compressive stress in nickel-based alloy 600 introduced by WJP and buffing stress improving treatments has been investigated. Hardness reduction behavior in WJP and buffing processed samples during thermal aging has been found to follow the Johnson-Mehl-Avrami equation and the rate constant for hardness reduction to be expressed by the Arrhenius equation. EBSD crystal orientation analysis has confirmed that the strain is introduced mainly in the surface region. Positron lifeti...
英字タイトル:
Mechanism for stress relaxation behavior of WJP and buffing stress improving treatments
英字タイトル:
Mechanism for stress relaxation behavior of WJP and buffing stress improving treatments
第17回
α汚染遠隔計測における3次元空間再構築技術の開発
著者:
坂本 直弥,大甕 舜一朗,三浦 崇広,久米 直人,松崎 謙司,宮原 康文,高木 純一,（東芝ESS,国際廃炉研究開発機構）
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1F 3D reconstruction Alpha Camera Alpha contamination Decommissioning
坂本 直弥,大甕 舜一朗,三浦 崇広,久米 直人,松崎 謙司,宮原 康文,高木 純一,（東芝ESS,国際廃炉研究開発機構）
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1F 3D reconstruction Alpha Camera Alpha contamination Decommissioning
Alpha Camera has been developed to check the alpha contamination of solid wastes generated during decommissioning of Fukushima Daiichi Nuclear Power Station (1F). A lot of measurements are needed to reveal the alpha contamination distributions due to the narrow field of view of the Alpha Camera. Therefore, in this paper, we propose a novel approach which reconstructs the divided measurement data in a three-dimensional space to identify the contaminated area easily.
In primitive demonstration using new recon...
英字タイトル:
Development of 3D reconstruction for remote alpha contamination measurement
英字タイトル:
Development of 3D reconstruction for remote alpha contamination measurement
第17回
α汚染遠隔計測技術現場適用のための開発
著者:
大甕 舜一朗,坂本 直弥,久米 直人,隅田 晃生,岡崎 幸基,湯原 勝,宮原 康文,高木 純一,（東芝ESS,国際廃炉研究開発機構）
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1F Alpha contamination Decommissioning Detector PMT
大甕 舜一朗,坂本 直弥,久米 直人,隅田 晃生,岡崎 幸基,湯原 勝,宮原 康文,高木 純一,（東芝ESS,国際廃炉研究開発機構）
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1F Alpha contamination Decommissioning Detector PMT
Alpha Camera is developed as a remotely-operated detector to check the alpha contamination of wastes generated during decommissioning of Fukushima Daiichi Nuclear Power Station. The smear method is currently used to check the alpha contamination inside the plant. However, a large amount of waste will be generated from future decommissioning. Therefore, in order to reduce the exposure of workers, a remotely-operated alpha detector with wide range is needed.
In this paper, to confirm that the Alpha Camera can...
英字タイトル:
Development of remote alpha contamination measurement detector for field application
英字タイトル:
Development of remote alpha contamination measurement detector for field application
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