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第12回
補修の規格 －保全活動における是正措置（補修等）の重要性－
著者:
青木 孝行,Takayuki AOKI,高木 敏行,Toshiyuki TAKAGI
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For creating a corrective measure plan for industrial plant components, it is very important to have a well-grounded basis. Therefore, this paper proposes a method for determining the following three elements of such a plan: an equipment to be repaired, a corrective measure method to be adopted, and a timing of its implementation using a rational approach. And the importance of corrective measure in plant maintenance is also discussed. ...
英字タイトル:
Codes and Standards in Repair and Replacement Process .Importance of Corrective Action in Maintenance Activities
第12回
補修の規格 －取組状況と課題－
著者:
小山 幸司,Koji KOYAMA,北条 公伸,Kiminobu HOJO
発刊日:
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When Repair and Replacement Process (RRP) for maintenance of facilities of operating nuclear power plants is applied based on the construction code, many difficulties may arise because of spatial or radioactive restriction compared to doing for facilities under construction. For this reason, industries have been developed maintenance technologies and provided guidelines and codes for the repair for the facilities of operating plants under those restricted conditions. But, in fact, these guidelines and ...
英字タイトル:
Codes and Standards in Repair and Replacement Process : Status and Issues
第12回
補修の規格－技術評価上の課題－
著者:
菅野 眞紀,Masanori KANNO
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As described in the IAEA Safety standards both No. SSG-25 “PSR for NPPs” and No.NS-G-2.12 “Ageing Management for NPPs”, maintenance activities for SSC is very important. Physical ageing of SSCs may increase the probability of common cause failures, which could result in the impairment of one or more levels of protection provided by the defense in depth concept. Therefore, Inspection, evaluation and repair & replacement in “Standards for Nuclear Power Generation Equipment (Maintenance Standards) for JSM...
英字タイトル:
Codes and Standards in Repair and Replacement Process . Concern on the technical evaluation by Nuclear Regulatory Agency－
第12回
試験片表面観察による機械構造用炭素鋼の 疲労き裂成長予測モデルの検討
著者:
石澤 輝士,Terushi ISHIZAWA,北田 孝典,Takanori KITADA,中村 隆夫,Takao NAKAMURA,釜谷 昌幸,Masayuki KAMAYA
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Cumulative Usage Factor (CUF) is currently used for fatigue design and management to prevent fatigue failure. Fatigue damage is evaluated by CUF but CUF doesn’t show the real extent of fatigue damage and cannot be used for probabilistic index for risk assessment. Therefore, in order to clarify relation between CUF and damage state, the introduction of postulated crack growth curve (P-curve) of stainless steel was examined by Kamaya [1]. This curve was defined by single crack growth curve made from fati...
英字タイトル:
Study on Fatigue Crack Growth Prediction Model of Carbon Steel based on Surface Observation of Fatigue Test Specimen
第12回
超音波フェーズドアレイを用いた 水中環境可視化技術の開発：水中形状計測
著者:
河野 尚幸,Naoyuki KONO,森 勇人,Hayato MORI,小林 亮介,Ryosuke KOBAYASHI
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For safety and early decommissioning of Fukushima, internal survey techniques have been expected to gain an understanding of the state of Fukushima Dai-ichi Nuclear Power Station. Underwater operation and survey is considered to be necessary for vessels and buildings partially filled with retained water. As a complementary of optical instrumentation, ultrasonic underwater visualization techniques have been important for recognizing environment and obstacles for supporting remote operation. In this stud...
英字タイトル:
Development of visualization techniques for underwater environment using ultrasonic array sensors: shape measurement
第12回
超高純度ステンレス鋼(EHP 合金)の環境適用性評価
著者:
江藤 淳二,Junji ETOH,芦田 高規,Takaki ASHIDA,落合 孝正,Takamasa OCHIAI,木内 清,Kiyoshi KIUCHI,滝沢 真之,Masayuki TAKIZAWA,中山 準平,Junpei NAKAYAMA
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An elemental factor on the crack propagation mechanism of SCC observed in LWRs component materials made of non-sensitization stainless steels is examined with respect to the local steam corrosion in cracks by atomic oxygen formed at the wall surface under the irradiation of γray. The excellent oxidation resistance of type 25Cr-35Ni EHP steel with forming the protective double layer oxides is observed up to 600℃. On the other hand, the oxidation of type 316L steel with non-protective single oxide is acc...
英字タイトル:
Environmental compatibility evaluation of extra high purity stainless steel (EHP alloy)
第12回
軽水炉保全最適化のための統合型シミュレータDr. Mainte による ヒューマンエラーの影響とその低減効果の検討
著者:
礒部 仁博,Yoshihiro ISOBE,匂坂 充行,Mitsuyuki SAGISAKA,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,高坂 徹,Toru KOUSAKA,松本 聡司,Satoshi MATSUMOTO,吉村 忍,Shinobu YOSHIMURA
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Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for representative components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement ...
英字タイトル:
Effects of Human Error and its Reduction Analyzed by Dr. Mainte, Integrated Simulator of Maintenance Optimization of LWRs
第12回
運転プラントにおけるシステム安全の考え方
著者:
宮野 廣,Hiroshi MIYANO,山口 彰,Akira YAMAGUCHI,出町 和之,Kazuyuki DEMACHI,高田 孝,Takashi TAKATA,荒井 滋喜,Shigeki ARAI,杉山 直紀,Naoki SUGIYAMA
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The total system design on Nuclear Plant ensures “Nuclear safety” with making practically achievable efforts to prevent and mitigate nuclear and radiological accidents. The performance based system design with “Defence in depth (D-I-D)” has been laid out as the key means in “preventing accidents”, “controlling escalation to serious consequences”, and “preventing harmful consequences to the public”. D-I-D is extended to the management of severe accidents, and is an approach intended to provide protectio...
英字タイトル:
Concept of System Safety on Operating Nuclear Power Plant
第12回
銀ゼオライトを用いた高除染性フィルターベントシステムの開発
著者:
奈良林 直,Tadashi NARABAYASHI,川村 慎一,Shinichi KAWAMURA
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Fukushima Daiichi NPP accident would be terminated, if sufficient accident countermeasures, such as water proof door, mobile power, etc. In case of Europe, it had already installed the heat removal system and filtered containment venting system (FCVS) from the lessons of TMI and Chernobyl Accidents. The new regulatory standard, the filtered vent system (FCVS) should be installed, and prevent the radioactive material in case of the severe accident and the overpressure breakage prevention of a primary co...
英字タイトル:
Development of High Efficiency Filtered Containment Venting System by using AgX
第12回
電動機電流診断装置（GA-500）の開発と適用事例
著者:
金子 修一,Syuichi KANEKO,迫 孝司,Takashi SAKO
発刊日:
公開日:
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We developed a diagnostic device that utilizes the Motor Current Signature Analysis (MCSA) to clarify the frequency domain to be focused by collecting the data which simulated various abnormalities in experimental apparatus. In addition, we found a correlation between the extent of the level and the abnormal of the generated frequency, and developed criteria. ...
英字タイトル:
The Development of the Motor Current Diagnosis Device (GA-500) and the Application Example
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