田中 正暁
著者に関連した記事は4件です。
更新情報
第14回
PIRT手法を用いた研究開発段階発電用原子炉の保守管理における要検証劣化メカニズムの抽出方法に関する検討
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
Degradation Mechanism Graded Approach Operational Experience Sodium-Cooled Fast Reactor
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
Degradation Mechanism Graded Approach Operational Experience Sodium-Cooled Fast Reactor
In a previous paper, the authors discussed maintenance management suitable to R&D-level nuclear power plants, and made proposals. One of key proposals was to enhance knowledge on potential degradation mechanisms specific to a new reactor type by accumulating operational experience. It was noted that validation of R&D knowledge in actual plant conditions is important. In this study, a method for identifying degradation mechanisms to be validated by the PIRT (Phenomena Identification and Ranking Table) p...
英字タイトル:
Study on a Method for Identifying Degradation Mechanisms to be Validated in Maintenance Management of R&D-Level Nuclear Power Plants Using the PIRT Process
英字タイトル:
Study on a Method for Identifying Degradation Mechanisms to be Validated in Maintenance Management of R&D-Level Nuclear Power Plants Using the PIRT Process
論文
先進的なナトリウム冷却高速炉の炉心出口部における サーマルストライピング現象に関する水流動試験 (1)制御棒周辺部の温度変動緩和対策の提案
著者:
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
A design study of an advanced sodium-cooled fast reactor (Advanced-SFR) has been conducted in Japan Atomic Energy Agency (JAEA). Hot sodium from the fuel assembly can mix with cold sodium from the control rod (CR) channel and the blanket assemblies at the bottom plate of the Upper Internal Structure (UIS). Temperature fluctuation due to mixing of the fluids at different temperature between the core outlet and cold channel may cause high cycle thermal fatigue on the structure around the bottom of UIS. A wate...
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of an Advanced Sodium-cooled Fast Reactor? (1) Proposal of Countermeasures to Mitigate Temperature Fluctuations around Control Rods?
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of an Advanced Sodium-cooled Fast Reactor? (1) Proposal of Countermeasures to Mitigate Temperature Fluctuations around Control Rods?
論文
先進的なナトリウム冷却高速炉の炉心出口部における サーマルストライピング現象に関する水流動試験 (2)径方向ブランケット燃料集合体周辺部の 温度変動緩和対策の提案
著者:
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
Focusing on the thermal striping phenomena that occurs at a bottom of the internal structure of an advanced sodium-cooled fast reactor (Advanced-SFR) that has been designed by the Japan Atomic Energy Agency, a water experiment using a 1/3 scale 60 degree sector model simulating the upper plenum of the Advanced-SFR has been conducted to examine countermeasures for the significant temperature fluctuation generated around the bottom of Upper Internal Structure (UIS). In the previous paper, we reported the effe...
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of?an Advanced Sodium-cooled Fast Reactor? (2) Proposal of Countermeasures to Mitigate Temperature Fluctuations?around Radial Blanket Fuel Assemblies?
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of?an Advanced Sodium-cooled Fast Reactor? (2) Proposal of Countermeasures to Mitigate Temperature Fluctuations?around Radial Blanket Fuel Assemblies?
第2回
異温度流体混合における熱流動特性の評価
著者:
菅原 良昌,Yoshimasa SUGAWARA,結城 和久,Kazuhisa YUKI,Hoseini Seyed MOHAMMAD,橋爪 秀利,Hidetoshi HASHIZUME,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
Degree Bend Fluid Mixing Secondary Flow Temperature Fluctuation Thermal Fatigue
菅原 良昌,Yoshimasa SUGAWARA,結城 和久,Kazuhisa YUKI,Hoseini Seyed MOHAMMAD,橋爪 秀利,Hidetoshi HASHIZUME,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
Degree Bend Fluid Mixing Secondary Flow Temperature Fluctuation Thermal Fatigue
In a process of hot and cold fluid mixing, temperature fluctuation in the fluid can occur. When this fluctuation is caused by unstable fluid mixing process, the surrounding structure would be damaged by high-cycle thermal fatigue. This phenomenon is observed in various nuclear power plants, which means it is important to investigate the relation between the fluid mixing process and the thermal fatigue. When there exists a 90-degree bend i n the upstream of the mixing area, the fluid mixing process becomes ...
英字タイトル:
Estimation on the thermal hydraulic characteristics in a non-isothermal fluid mixing
英字タイトル:
Estimation on the thermal hydraulic characteristics in a non-isothermal fluid mixing