第14回
レジリエンス評価法の高速炉への適用性に関する基礎的検討
著者:
鈴木 正昭,Masaaki SUZUKI,出町 和之,Kazuyuki DEMACHI,高屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA
発刊日:
公開日:
キーワードタグ:
We have proposed new indices for evaluating resilience, that is, the response margin and response reliability of a nuclear power plant during an accident and detailed procedure for assessing those indices. In this study, the resilience of a simple fast reactor plant model is evaluated according to the indices. The applicability of the resilience evaluation method to fast reactor plants is then discussed from the viewpoints of reflecting the characteristics of each reactor type....
英字タイトル:
Fundamental Study on Applicability of Resilience Evaluation Method to Fast Reactor Plants
第5回
中性子残留応力測定法を用いた実機経年化溶接継手および補修溶接継手の健全性評価に関する基礎的検討
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
発刊日:
公開日:
キーワードタグ:
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. For this reason, it is needed to establish the aged weld joint integrity assessment method for future FBR compon ents. Additionally, since it is expected to employ the repair weld for aged structural components, it is essential to investigate the effect of repair weld. To investigate the influence of high temperature-long service...
英字タイトル:
Basic investigation of aging weld joint and repair weld joint integrity assessmentusing neutron residual stress measurement method
第7回
漏えい磁束密度による照射損傷評価のための測定技術の改良
著者:
今野 将太郎,Shotaro KONNO,高屋 茂,Shigeru TAKAYA,永江 勇二,Yuji NAGAE,山県 一郎,Ichiro YAMAGATA,小川 竜一郎,Ryuichiro OGAWA,赤坂 尚昭,Naoaki AKASAKA,西野入 賢治,Kenji NISHINOIRI
発刊日:
公開日:
キーワードタグ:
We are developing a method for evaluation of irradiation damage on structural materials in nuclear plants by using change in magnetic flux density due to irradiation damage. In this study, the magnetic flux density measurement technique has been improved by introducing a new magnetizer which enables local magnetizing by contacting the sample surface. We can magnetize samples, especially ferromagnetic samples, more precisely co mpared to the existing method. Furthermore, the new method can remove many limi...
英字タイトル:
Improvement of Magnetic Flux Density Measurement Techniquefor Irradiation Damage Evaluation
第5回
漏えい磁束密度測定による照射誘起応力腐食割れ感受性評価
著者:
高屋 茂,Shigeru TAKAYA,根本 義之,Yoshiyuki NEMOTO,内一 哲哉,Tetsuya UCHIMOTO,欅田 理,Satoshi KEYAKIDA
発刊日:
公開日:
キーワードタグ:
In a previous study, authors showed experimentally the correlation between leakage magnetic flux density and irradiation assisted stress corrosion cracking susceptibility of high purity model austenitic stainless ste els. This study aimed to investigate mechanism of the correlation. Tensile test at elevated temperature and aging test were conducted on materials simulating irradiation-induced segregation, and leakage magnetic flux density was measured before and after these tests in order to study the influ...
英字タイトル:
Evaluation of Sensitivity to Irradiation Assisted Stress Corrosion Crackingby Measurement of Leakage Magnetic Flux Density
論文
照射損傷評価のための遠隔操作式振動試料型磁力計の開発
著者:
高屋 茂,Shigeru TAKAYA,山県 一郎,Ichiro YAMAGATA,市川 正一,Shoichi ICHIKAWA,永江 勇二,Yuji NAGAE,若井 栄一,Eiichi WAKAI
発刊日:
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キーワードタグ:
The remote operated vibrating sample magnetometer (VSM) for neutron irradiated samples has been developed. The maximum range of applied magnetic field is more than ±0.5/?0 A/m, and the resolution of magnetic moment is higher than 5 ×10-8 A?m2. The hysteresis loops of neutron irradiated samples were measured by this VSM, and the relationships between dose, which is one of epresentative irradiation parameter, and magnetic properties such as magnetic coercive force were examined. As result, it was revealed tha...
英字タイトル:
Development of Remote Operated Vibrating Sample Magnetometer for Evaluation of Irradiation Damage
第6回
照射損傷評価のための遠隔操作式振動試料型磁力計の開発
著者:
高屋 茂,Shigeru TAKAYA,山県 一郎,Ichiro YAMAGATA,永江 勇二,Yuji NAGAE,若井 栄一,Eiichi WAKAI,青砥 紀身,Kazumi AOTO
発刊日:
公開日:
キーワードタグ:
The remote operated vibrating sample magnetometer (VSM) for neutron irradiated samples has been developed. The maximum range of applied magnetic field is more t han £0.5/10 A/m, and the resolution of magnetization is higher than 5 x10-A'm2. The magnetization curves of neutron irradiated samples were measured by this VSM , and the relationships between dose, which is one of representative irradiation parameter, and magnetic properties such as magnetic coercive force. As result, it was revealed that there a...
英字タイトル:
Development of Remote Operated Vibrating Sample Magnetometerfor Evaluation of Irradiation Damage
論文
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. Finally, an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (1)基本要件
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (1) Basic Requirements
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (2)適用事例
著者:
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applie...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (2) case study
第14回
研究開発段階発電用原子炉の特徴を考慮した保守管理の提案 (3) 配管支持構造物への適用事例
著者:
相澤 康介,Kosuke AIZAWA,髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
発刊日:
公開日:
キーワードタグ:
One of important mission of nuclear power plants (NPP) at R&D stage is to develop maintenance program for commercial reactors step by step securing safety. Basic principles of maintenance management for NPP at R&D stage were proposed. In this paper, applications for maintenance program on piping support of prototype sodium cooled fast breeder reactor Monju are studied on the basis of the proposed basic principles of maintenance management for NPP at R&D stage. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (3) Application to piping support