99件が見つかりました。

並び替え
第12回
PASCAL-ECを用いた減肉配管のフラジリティ評価
著者:
山口 義仁,Yoshihito YAMAGUCHI
発刊日:
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A probabilistic analysis code PASCAL-EC (PFM Analysis of Structural Components in Aging LWR - Erosion and Corrosion) has been improved for evaluating structural integrity of wall-thinned pipes on the basis of the Monte Carlo method. In order to perform the fragility evaluation for wall-thinned pipes, several functions are introduced to PASCAL-EC in this work, such as a probabilistic evaluation model to consider the uncertainty of seismic response stress, a simple evaluation model to considered the incr...
英字タイトル:
Fragility Evaluation of Wall-thinned Pipes Using PASCAL-EC
第12回
PD 資格試験開始から9 年の実施状況
著者:
渡辺 恵司,Keiji WATANABE,東海林 一,Hajime SHOHJI,秀 耕一郎,Koichiro HIDE,太田 丈児,Joji OHTA
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The PD Center of Central Research Institute of Electric Power Industry (CRIEPI) commenced Performance Demonstration examinations for flaw depth sizing of austenitic stainless steel pipes in March 2006. At the end of FY 2014, 42 examination sessions have been completed and 53 candidates have passed the examination. The total number of tests administered including re-tests and re-certification was 99. Passed candidates can perform depth sizing of IGSCC flaws with a high level of accuracy. For the final d...
英字タイトル:
Current status for nine years after the start of PD qualification examination in Japan
第12回
SA 関連の原子力学会の標準策定の活動状況
著者:
河井 忠比古,Tadahiko KAWAI
発刊日:
公開日:
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Atomic Energy Society of Japan (AESJ) has developed various consensus standards under the policy of neutral, fairness, and openness, which adopts the latest technical knowledge to secure the safety of nuclear power plants and other nuclear facilities. With Fukushima Dai-ichi Accident which happened in 2011, our goal in the short term was to immediately develop various consensus standards as detailed specifications standards corresponding to the newly established regulatory requirements in 2015. Our goa...
英字タイトル:
The Current Activities to Develop Consensus Standards related to Severe Accident in Atomic Energy Society of Japan (AESJ)
第12回
オーステナイトステンレス鋼の中性子照射による磁気特性変化に関する研究
著者:
根本 義之,Yoshiyuki NEMOTO,大石 誠,Makoto OHISHI,伊藤 正泰,Masayasu ITO,加治 芳行,Yoshiyuki KAJI
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Authors previously reported that Eddy current method and AC magnetization method have potential to be applied for development of diagnostic technics to detect the sign of augmentation of the irradiation assisted stress corrosion cracking (IASCC) susceptibility before cracking on the austenitic stainless steel used as structural material in nuclear power plants. In typical austenitic stainless steels such as type304, magnetic ferrite phase would exist in the alloy before irradiation, and it is concerned...
英字タイトル:
Study on Magnetic Property Change on Neutron Irradiated Austenitic Stainless Steel
第12回
オーステナイト系ステンレス鋼316FR 鋼の供用中クリープ寿命予測法
著者:
中曽根 祐司,Yuji NAKASONE,鈴木 駿,Hayao SUZUKI
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The present paper proposes new creep life prediction methods that can be used in situ as an in-service inspection tool for the condition based monitoring of high-temperature structure components of 316FR stainless steel. The methods are based on two types of the modified theta methods and the combination of the modified and omega methods are applied to creep deformation data measured in the creep tests made at different applied stress levels at 823-923 K in air. Creep lives were predicted by the propos...
英字タイトル:
In Situ Creep Life Prediction Methods for Austenitic Stainless Steel 316FR
第12回
オーステナイト系ステンレス鋼の 等二軸応力下における疲労き裂進展挙動に関する検討
著者:
飯田 智,Satoshi IIDA,北田 孝典,Takanori KITADA,中村 隆夫,Takao NAKAMURA,釜谷 昌幸,Masayuki KAMAYA
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To prevent degradation at Nuclear Power Plants (NPPs) by maintenance activity, fatigue evaluation should be improved to be more accurate. Studies of crack growth under equi-biaxial fatigue which is caused by thermal stress have been conducted for these purposes. Previous study shows that crack growth rate under equi-biaxial stress is faster than under uniaxial one. But the comparison is not quantitative. In this study, the difference of crack growth rate between equi-biaxial and uniaxial is confirmed q...
英字タイトル:
Study on the Behavior of Fatigue Crack Growth of Austenitic Stainless Steel under Equi-biaxial Stress
第12回
クランプを用いた埋設配管補修技術
著者:
綿引 健二,Kenji WATAHIKI,石井 貴広,Takahiro ISHII,鋤柄 光二,Koji SUKIGARA,算用子 裕孝,Hirotaka SANYOSHI,伊波 慎一,Shinichi INAMI
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Treated water of The Tokai Reprocessing Plant used for cooling water and fire fighting water, is supplied by the steel pipes. These pipes are laid down under the ground or in the trench. Treated water had leaked, because the part of the underground pipe flange corrosion. The cause of this breakage was presumed that the pipe flange has been loaded the stress continuously. The stress generated depend of that the underground pipes sank with the ground subsidence by influence of the 2011 earthquake of the ...
英字タイトル:
Adaptation of the Treated Water Pipe Maintenance Technology useing Clamp
第12回
システム安全評価のためのレジリエンス指標の 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,村上 健太,Kenta MURAKAMI,糸井 達哉,Tatsuya ITOI,笠原 直人,Naoto KASAHARA,宮野 廣,Hiroshi MIYANO,中村 隆夫,Takao NAKAMURA,荒井 滋喜,Shigeki ARAI,釜谷 昌幸,Masayuki KAMAYA,松本 昌昭,Masaaki MATSUMOTO
発刊日:
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We have developed a new index called Resilience index, which evaluate the reliability of system safety of nuclear power plant under severe accident by considering the capability to recover from the situation the system safety function was lost. In this paper, a detailed evaluation procedure for the Resilience index was described. System safety of a PWR plant under severe accident was then assessed according to the Resilience index concept to discuss applicability of the index. We found that the Resilie...
英字タイトル:
Fundamental Study on Applicability of Resilience Index for System Safety Assessment
第12回
シビアアクシデントコードMAAP の改良と事故解析
著者:
藤井 正,Tadashi FUJII,酒井 健,Takeshi SAKAI,西田 浩二,Koji NISHIDA,小島 良洋,Yoshihiro KOJIMA,千原 瑠為,Rui CHIHARA,狩野 喜二,Yoshiji KARINO
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As part of efforts to decommissioning of the Fukushima Daiichi nuclear power plants (NPP), model enhancement of severe accident analysis code “MAAP” and accident progression analyses for Fukushima Daiichi NPP have been conducted for preparation of fuel debris retrieval. The object of this study is estimation of reactor core and containment vessel status for decision of planning the debris retrieval method based on the accident progression analysis results. This report summarizes the model improvement ...
英字タイトル:
Enhancement of Severe Accident Code MAAP and Accident Progression Analysis for Fukushima Daiichi Nuclear Power Plant
第12回
ステンレス鋼の低サイクル疲労に対するき裂成長予測手順
著者:
釜谷 昌幸,Masayuki KAMAYA
発刊日:
公開日:
キーワードタグ:
In order to show validity of the strain intensify factor for predicting crack growth in the low-cycle fatigue regime, fatigue crack growth tests using Type 316 stainless steel in room temperature were reviewed. It was shown that the crack growth rates correlated well with the equivalent stress intensify factor, which was derived using strain range instead of stress range. Furthermore, the effective equivalent stress intensify factor derived using the effective strain range exhibited excellent correlati...
英字タイトル:
Crack Growth Prediction of Stainless Steel for Low-Cycle Fatigue Regime