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第9回
高温疲労き裂進展下限界値と負荷履歴依存
著者:
岡崎 正和,Masakazu OKAZAKI,岩崎 亮,Ryou IWASAKI,笠原 直人,Naoto KASAHARA
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Abstract Effect of loading history on the high cycle fatigue crack propagation behavior was experimentally studied in SUS 316 stainless steel, paying a special attention to an interaction between low-cycle thermo-mechanical fatigue loading and high cycle fatigue one in the fatigue crack propagation rates. The experimental results clearly demonstrat ed that the interaction was significant. It was shown that the stress ratio which was built-up under an influence of previous loading history made a major contr...
英字タイトル:
Fatigue Crack Threshold Depending on Loading History.
第9回
高温超音波センサの開発
著者:
馬場 淳史,Atsushi BABA,武捨 義則,Yoshinori MUSHA,小池 正浩,Masahiro KOIKE,大谷 健一,Kenichi OTANI,平塚 真弘,Masahiro HIRATSUKA
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Abstract Structural health monitoring (SHM) techniques are needed to maintain the reliability of power plants for long term operation. The high temperature transducers are necessary to realize SHM (monitor wall thickness of the pipings, crack growth in the materials and material evaluation) under the working condition of power plants. We have evaluated lithium niobate (LiNb03) single crystal which is well known as a high Curie temperature piezoelectric material to develop high temperature ultrasonic transd...
英字タイトル:
Development of High Temperature Ultrasonic Transducers
第9回
高経年化技術評価の高度化 - コンクリート構造物の長期耐久性評価 -
著者:
橘高 義典,Yoshinori KITSUTAKA,橘高 義典,Yoshinori KITSUTAKA
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In this paper, method on the aging evaluation in nuclear power plant concrete structures was investigated. Problems on the durability evaluation of reinforced concrete structures were pointed out and an evaluation framew ork was considered. In view of the importance of evaluating the degree of deterioration of reinforced concrete structures, relationships should be formulated among the number of years elapsed, 1, the amount of action of a deteriorative factor, F, the degree of material deterioration, D, an...
英字タイトル:
Study of System Safety Evaluation on LTO of National Project- Long Term Durability Evaluation of Concrete Structures -
第9回
高経年化技術評価の高度化 -安全規制研究の取り組み-
著者:
関村 直人,Noato SEKIMURA,宮野 廣,Hiroshi MIYANO
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Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as “the first stage“ from 2006 FY to 2010 FY whose objective is “Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NNPs.Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national projec...
英字タイトル:
Study of System Safety Evaluation on LTO of National Project - NISA Safety Research Project on System Safety of Nuclear Power Plants
第9回
高経年化技術評価の高度化 -稼働プラントの経年劣化とシステム安全評価-
著者:
宮野 廣,Hiroshi MIYANO,山口 彰,Akira YAMAGUCHI,出町 和之,Kazuyuki DEMACHI,松本 昌昭,Masaaki MATSUMOTO
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Since the Fukushima Dai-ichi accident, the importance of “system safety'' has been recognized anew. Particularly, system safety assessment of plants in operation from the various degradation perspectives, specifically, transition of time is very important. Accordingly, functional degradation will be the assessment target of degradation, and the changes in the safety standards and the concept of safety will be dealt with; where, the reliability assessment will be made on the consolidation of important func...
英字タイトル:
Study of System Safety Evaluation on LTO of National Project - Functional Degradation and System Safety Assessment of Nuclear Plants in Operation
第9回
高経年化技術評価の高度化 一原子炉圧力容器の健全性評価一
著者:
鬼沢 邦雄,Kunio ONIZAWA,真﨑 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA
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Abstract To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment meth ods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors have initiated extensive research on the improvement of structural integrity assessment methods of RP Vs. In this paper, we describe some research results obtained from the first-year...
英字タイトル:
Study of System Safety Evaluation on LTO of National ProjectStructural Integrity Assessment of Reactor Pressure Vessels
第9回
高速炉の蒸気発生器伝熱管用 マルチコイル型 RF-ECT センサの開発
著者:
山口 智彦,Toshihiko YAMAGUCHI,ミハラケ ビック,Ovidiu MIHALACHE,上田 雅司,Masashi UEDA,山下 卓哉,Takuya YAMASHITA
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A new design was adopted for SG of JSFR (Japan Sodium-cooled Fast Reactor) using double-wall tubes. The present paper estimates and assess the defects detection in double-wall SG tubes for JSFR using Multiple RF-ECT sensor. We confirmed that proposed Multiple RF-ECT sensor has a high sensitivity to detect small defects....
英字タイトル:
Development of Multi-coil RF-ECT Sensor for JSFR SG tubes
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