更新情報
第5回
SUS304鋼におけるクリープ歪と強磁性相の生成
著者:
白木 厚寛,Atsuhiro SHIRAKI,塚田 祐貴,Yuhki TSUKADA,村田 純教,Yoshinori MURATA,高屋 茂,Shigeru TAKAYA,小山 敏幸,Toshiyuki KOYAMA
発刊日:
公開日:
キーワードタグ:
creep dislocation strain transformation
白木 厚寛,Atsuhiro SHIRAKI,塚田 祐貴,Yuhki TSUKADA,村田 純教,Yoshinori MURATA,高屋 茂,Shigeru TAKAYA,小山 敏幸,Toshiyuki KOYAMA
発刊日:
公開日:
キーワードタグ:
creep dislocation strain transformation
This study demonstrates the mechanism of y ? a transformation in creep test on the basis of the energy o f the system. The experimental result shows that the strain energy around M23Co carbide becomes very high due to dislocations stored during creep. As a result, the system free energy in the local region near the carbide increases with increasing creep time but it decreases by the formation of ferromagnetic a phase....
英字タイトル:
Formation of ferromagnetic phase in SUS304 steel by strain energy stored during creep test
英字タイトル:
Formation of ferromagnetic phase in SUS304 steel by strain energy stored during creep test
第13回
ASME B&PV Code Section XI におけるシステム化規格概念に基づく Code Case の策定活動 Development of a Code Case Based on the System Based Code Concept for ASME Boiler and Pressure Vessel Code Section XI
著者:
高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
ASME B&PV Code Section XI Inservice Inspection Reliability Evaluation System Based Code
高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
ASME B&PV Code Section XI Inservice Inspection Reliability Evaluation System Based Code
This paper describes the outline of a Code Case that is being developed for ASME Boiler and Pressure Vessel Code Section XI Division 3, Rules for Inspection and Testing of Components of Liquid-Metal Cooled Plants. The logic flow of the Code Case has been developed using the System Based Code concept and the Code Case provides alternative inservice inspection programs to sodium-cooled fast reactor components based on safety considerations and structural reliability evaluations. ...
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
第6回
SUS304 鋼のクリープ変形における強磁性相生成のPhase-field シミュレーション
著者:
塚田 祐貴,Yuhki TSUKADA,白木 厚寛,Atsuhiro SHIRAKI,村田 純教,Yoshinori MURATA,森永 正彦,Masahiko MORINAGA,高屋 茂,Shigeru TAKAYA,小山 敏幸,Toshiyuki KOYAMA
発刊日:
公開日:
キーワードタグ:
Austenitic Steel Ferromagnetic Phase Phase Transformation Phase-Field Method
塚田 祐貴,Yuhki TSUKADA,白木 厚寛,Atsuhiro SHIRAKI,村田 純教,Yoshinori MURATA,森永 正彦,Masahiko MORINAGA,高屋 茂,Shigeru TAKAYA,小山 敏幸,Toshiyuki KOYAMA
発刊日:
公開日:
キーワードタグ:
Austenitic Steel Ferromagnetic Phase Phase Transformation Phase-Field Method
The formation of the ferromagnetic a phase during creep deformation in SUS304 steel was simulated by a hase-field method. In order to consider the precipitation and growth of the phase simultaneously, we have onstru cted a model based on experimental results. In this model, strain energy stored near M23Co carbide uring creep deformation increases the driving force for precipitation of the a phase. This strain energy is stimated on the basis of distribution function of dislocation density in space near the ...
英字タイトル:
Phase-field simulation on the formation of ferromagnetic phaseduring creep deformation in SUS304 steel
英字タイトル:
Phase-field simulation on the formation of ferromagnetic phaseduring creep deformation in SUS304 steel
第2回
SUS304 鋼の高温疲労損傷初期段階における磁気特性変化
著者:
高屋 茂,Shigeru TAKAYA,永江 勇二,Yuji NAGAE
発刊日:
公開日:
キーワードタグ:
Fatigue Damage in High Temperature Environment Magnetic Property Nondestructive Estimation of Material Degradation SUS304 StainlessSteel
高屋 茂,Shigeru TAKAYA,永江 勇二,Yuji NAGAE
発刊日:
公開日:
キーワードタグ:
Fatigue Damage in High Temperature Environment Magnetic Property Nondestructive Estimation of Material Degradation SUS304 StainlessSteel
Developing a precise nondestructive estimation method of material degradation before crack initiation will contribute to enhancement of safety and economical efficiency of a fast breeder reactor plant. Magnetic property is expected to be an effective indicator. In this study, fatigue t ests on SUS304 stainless steel at 650°C were conducted until transition hardening region, 25% and 50% of the number of cycles to fracture and the distribution of magnetic flux density from each sample was measured to reveal ...
英字タイトル:
Magnetic Property Change of SUS304 Stainless Steel at Initial State of Fatigue Damage in High Temperature Environment
英字タイトル:
Magnetic Property Change of SUS304 Stainless Steel at Initial State of Fatigue Damage in High Temperature Environment
論文
SUS304鋼の高温疲労損傷初期段階における磁気特性変化
著者:
高屋 茂,Shigeru TAKAYA,永江 勇二,Yuji NAGAE
発刊日:
公開日:
キーワードタグ:
Fatigue Damage in High Temperature Environment Magnetic Property Nondestructive Estimation of Material Degradation SUS304 Stainless Steel
高屋 茂,Shigeru TAKAYA,永江 勇二,Yuji NAGAE
発刊日:
公開日:
キーワードタグ:
Fatigue Damage in High Temperature Environment Magnetic Property Nondestructive Estimation of Material Degradation SUS304 Stainless Steel
Developing a precise nondestructive estimation method of material degradation before crack initiation will contribute to enhancement of safety and economical efficiency of a fast breeder reactor plant. Magnetic property is expected to be an effective indicator. In this study, fatigue tests on SUS304 stainless steel at 650°C were conducted until transition hardening region, 25% and 50% of the number of cycles to fracture and the distribution of magnetic flux density from each sample was measured to r...
英字タイトル:
Magnetic Property Change of SUS304 Stainless Steel at Initial State of Fatigue Damage in High Temperature Environment
英字タイトル:
Magnetic Property Change of SUS304 Stainless Steel at Initial State of Fatigue Damage in High Temperature Environment
第3回
「ASCC 感受性の予兆診断手法に関する研究
著者:
根本 義之,Yoshiyuki NEMOTO,上野 文義,Fumiyoshi UENO,永江 勇二,Yuji NAGAE,高屋 茂,Shigeru TAKAYA,吉武 庸光,Tsunemitsu YOSHITAKE,青砥 紀身,Kazumi AOTO,塚田 隆,Takashi TSUKADA
発刊日:
公開日:
キーワードタグ:
Austenitic Stainless Steel BWR FG sensor IASCC JRR-3 SSRT
根本 義之,Yoshiyuki NEMOTO,上野 文義,Fumiyoshi UENO,永江 勇二,Yuji NAGAE,高屋 茂,Shigeru TAKAYA,吉武 庸光,Tsunemitsu YOSHITAKE,青砥 紀身,Kazumi AOTO,塚田 隆,Takashi TSUKADA
発刊日:
公開日:
キーワードタグ:
Austenitic Stainless Steel BWR FG sensor IASCC JRR-3 SSRT
This study proposes a predictive monitoring method for irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels. High purity model austenitic stainless steel s were irradiated up to ldpa or 5dpa in JRR-3. IASCC susceptibility of the irradiated specimens was determined by scanning electro microscopy (SEM) on fractured surface of the specimens after slow strain rate tensile (SSRT) testing in high temperature water simulating boiling water reactor (BWR) conditions. Magnetic proper...
英字タイトル:
A Study of Testing Method for Predictive-Monitoring of IASCC Susceptibility
英字タイトル:
A Study of Testing Method for Predictive-Monitoring of IASCC Susceptibility
論文
「もんじゅ」点検期間長期化の要因分析及び 次世代高速炉の保全合理化案の提案 (2) ~低温停止期間における「もんじゅ」の保全計画分析~
著者:
豊田 晃大,Kodai TOYOTA,橋立 竜太,Ryuta HASHIDATE,高橋 慧多,eita TAKAHASHI,矢田 浩基,Hiroki YADA,高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
Fast reactor Maintenance Maintenance rationalization Monju Sodium
豊田 晃大,Kodai TOYOTA,橋立 竜太,Ryuta HASHIDATE,高橋 慧多,eita TAKAHASHI,矢田 浩基,Hiroki YADA,高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
Fast reactor Maintenance Maintenance rationalization Monju Sodium
次世代高速炉の合理的な設計や保全の最適化を実現するためには,もんじゅにおける点検長期化の要因を分析し,課題の整理と対策案を検討することが重要となる.本論文では,高速炉の稼働率向上を目的に,保全合理化検討のための概略的分析の結果を報告する.
具体的には,もんじゅの保全に関する全体傾向の把握及び保全合理化の余地が大きいと考えられる保全内容を抽出するため,もんじゅ保全計画に記載されている点検タスクの情報を分析した.また,得られた分析結果に対し,保全合理化の提案を行った....
英字タイトル:
Proposal of Maintenance Rationalization for Next-Generation Fast Reactors based on the Analysis of the Prolonged Maintenance of the Prototype Fast-Breeder Reactor in Japan, “Monju” (2) ~Analysis of Maintenance Plan of “Monju” in Reactor Cold Shutdown~
英字タイトル:
Proposal of Maintenance Rationalization for Next-Generation Fast Reactors based on the Analysis of the Prolonged Maintenance of the Prototype Fast-Breeder Reactor in Japan, “Monju” (2) ~Analysis of Maintenance Plan of “Monju” in Reactor Cold Shutdown~
論文
「もんじゅ」点検期間長期化の課題の分析から学ぶ次世代高速炉の保全合理化案の提案(1)~低温停止中の「もんじゅ」のプラント工程の分析~
著者:
橋立 竜太,Ryuta HASHIDATE,豊田 晃大,Kodai TOYOTA 高橋 慧多,Keita TAKAHASHI 矢田 浩基,Hiroki YADA 高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
Diesel Generator Fast Reactor Maintenance Maintenance Rationalization Monju Sodium
橋立 竜太,Ryuta HASHIDATE,豊田 晃大,Kodai TOYOTA 高橋 慧多,Keita TAKAHASHI 矢田 浩基,Hiroki YADA 高屋 茂,Shigeru TAKAYA
発刊日:
公開日:
キーワードタグ:
Diesel Generator Fast Reactor Maintenance Maintenance Rationalization Monju Sodium
本論文では、点検自体の期間も長く、その遅延が直接プラント工程に影響を及ぼすクリティカルパスの点検に着目し、もんじゅの点検に要する期間が長期化した要因を分析する。この要因に対し、次世代高速炉における合理的な保全を実現し、稼働率を向上させることを目的とした、次世代高速炉の設計や運用に反映すべき対策を検討した。...
英字タイトル:
Proposal of Maintenance Rationalization for Next-Generation Fast Reactors based on the Analysis of the Prolonged Maintenance of the Prototype Fast-Breeder Reactor in Japan, “Monju”? (1) ~Analysis of Plant Schedule of “Monju” in Cold Shutdown~
英字タイトル:
Proposal of Maintenance Rationalization for Next-Generation Fast Reactors based on the Analysis of the Prolonged Maintenance of the Prototype Fast-Breeder Reactor in Japan, “Monju”? (1) ~Analysis of Plant Schedule of “Monju” in Cold Shutdown~
論文
オーステナイト系ステンレス鋼溶接継手の金属組織と 残留応力に及ぼす実機での高温長時間使用および補修溶接の影響
著者:
小原 智史,Satoshi OBARA,高屋 茂,Shigeru TAKAYA,若井 隆純,Takashi WAKAI,浅山 泰,Tai ASAYAMA,鈴木 裕士,Hiroshi SUZUKI,齊藤 徹,Toru SAITOH,Laurent MARTIN
発刊日:
公開日:
キーワードタグ:
304SS 316LSS Austenitic Steel Aged Welded Joint Hardness Microstructure Repaired Welded Joint RESA RESA-Ⅱ Residual stress Used for 88000h at 526-545℃ in Phenix
小原 智史,Satoshi OBARA,高屋 茂,Shigeru TAKAYA,若井 隆純,Takashi WAKAI,浅山 泰,Tai ASAYAMA,鈴木 裕士,Hiroshi SUZUKI,齊藤 徹,Toru SAITOH,Laurent MARTIN
発刊日:
公開日:
キーワードタグ:
304SS 316LSS Austenitic Steel Aged Welded Joint Hardness Microstructure Repaired Welded Joint RESA RESA-Ⅱ Residual stress Used for 88000h at 526-545℃ in Phenix
For the commercialization of fast breeder reactors (FBR), it is essential to enhance the economic competitiveness by reduction of total cost by elongation of plant service period. In this point of view, it is important to establish the assessment method of integrity of aged weld joint and repair welding for the components of future long life FBR. In the present study, evolution of microstructure is evaluated for the 304SS-304SS weld joint which was used for 88,000h at 526-545°C in the French proto-typ...
英字タイトル:
Influence of FBR plant service and repair welding on microstructure and residual stress of austenitic stainless steel weld joint
英字タイトル:
Influence of FBR plant service and repair welding on microstructure and residual stress of austenitic stainless steel weld joint