Akikazu KURIHARA
著者に関連した記事は4件です。
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論文
ナトリウム中に噴出する不活性ガス不足膨張衝突噴流の 局所構造と対応するエロージョン試験法の開発
著者:
工藤 秀行,Hideyuki KUDOH,太田 淳己,Junki OHTA,杉山 憲一郎,Ken-ichiro SUGIYAMA,奈良林 直,Tadashi NARABAYASHI,大島 宏之,Hiroyuki OHSHIMA,栗原 成計,Akikazu KURIHARA
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キーワードタグ:
Erosion Liquid Droplet Impingement Liquid-Sodium Droplet Sodium-Cooled Fast Reactor Sodium-Water Reaction Steam Generator Underexpanded Supersonic-Jet Visualization
工藤 秀行,Hideyuki KUDOH,太田 淳己,Junki OHTA,杉山 憲一郎,Ken-ichiro SUGIYAMA,奈良林 直,Tadashi NARABAYASHI,大島 宏之,Hiroyuki OHSHIMA,栗原 成計,Akikazu KURIHARA
発刊日:
公開日:
キーワードタグ:
Erosion Liquid Droplet Impingement Liquid-Sodium Droplet Sodium-Cooled Fast Reactor Sodium-Water Reaction Steam Generator Underexpanded Supersonic-Jet Visualization
When a heat transfer tube wall in a steam generator of a sodium-cooled fast reactor fails, high-pressure steam leaks into low-pressure liquid sodium side. Then the high-temperature and highly corrosive reaction jet causes secondary failures of neighboring heat transfer tubes. The objective of the present study is to develop an experimental method to obtain data that is necessary to validate and improve a safety evaluation code on the sodium?water reaction. In the present paper, the methods of sodium?...
英字タイトル:
Development of Erosion Test Methods on Underexpanded Inert-Gas Impinging Jets Injected in Liquid Sodium
英字タイトル:
Development of Erosion Test Methods on Underexpanded Inert-Gas Impinging Jets Injected in Liquid Sodium
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
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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:
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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10回
高速増殖炉ＳＧ伝熱細管のＬＤＩによる急速減肉に関する研究
著者:
加藤 慶輔,Keisuke KATO,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TSUJI,千葉 豪,Go CHIBA,大島 宏之,Hiroyuki OHSHIMA,栗原 成計,Akikazu KURIHARA,内堀 昭寛,Akihiro UCHIBORI
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キーワードタグ:
FBR LDIE SG Two phase flow Wastage phenomena
加藤 慶輔,Keisuke KATO,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TSUJI,千葉 豪,Go CHIBA,大島 宏之,Hiroyuki OHSHIMA,栗原 成計,Akikazu KURIHARA,内堀 昭寛,Akihiro UCHIBORI
発刊日:
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キーワードタグ:
FBR LDIE SG Two phase flow Wastage phenomena
Wastage phenomena occur when a heat transfer tube is failed in a Steam Generator (SG) of Fast Breeder Reactor (FBR) and its mechanism is still unexplained. We focused on Liquid Droplet Impingement Erosion (LDIE) as a factor of the wastage phenomena and performed a basic study with a partial mock-up water test simulating a piping group in SG for quantitative evaluation of LDIE. First, we did visualization tests of high pressure and high speed jet into water. The test section consists of a failure heat ...
英字タイトル:
Study on Rapid Wastage due to Liquid Droplet Impingement on Heat Transfer Tube in SG of Fast Breeder Reactor
英字タイトル:
Study on Rapid Wastage due to Liquid Droplet Impingement on Heat Transfer Tube in SG of Fast Breeder Reactor