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第16回
FRPの健全性診断に向けた非破壊検査システム開発
著者:
藤吉 宏彰,石井 元武,礒部 仁博,（原燃工）,川島 崇利,（関西電子ビーム）,浦島 千裕,岡 隆之,鈎 忠志,（関西電力）
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キーワードタグ:
Fiber reinforced plastic (FRP) is used in a wide range of applications due to its light weight, high strength, excellent corrosion resistance and flexible processability. Although nuclear power plants may have a chance to use FRP as structural and equipment materials in the future, its radiation effect is not well known so far. Thus, we tried to evaluate its radiation degradation non-destructively using "AE (Acoustic Emission) digital hammering inspection". Two types of FRP test specimens of glass fiber and...
英字タイトル:
Development of nondestructive inspection system for soundness diagnosis of FRP
第16回
ITERにおける核融合炉の保守保全技術の進展
著者:
武田 信和,野口 悠人,丸山 孝仁,齋藤 真貴子,（量研機構）
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It is considered that most of maintenance operation of fusion reactors will be performed remotely because of high gamma-ray radiation inside the reactor. The ITER, an experimental fusion device constructed under the international collaboration, will test and confirm such remote maintenance technologies to realize remote maintenance in the DEMO reactors planned for demonstration of fusion energy. This report outlines remote maintenance technology of the ITER....
英字タイトル:
Progress of Maintenance Technology of Fusion Reactor for ITER
第16回
Mechanism　study　of　Directivity　of　TR　probe　for　Eddy　Current　Testing　of　Magnetic　Structural　Material
著者:
Shurui ZHANG,Sho TAKEDA,Tetsuya UCHIMOTO,Toshiyuki TAKAGI,Mitsuo HASHIMOTO,Ziyue XU,（東北大）,Yanzhen ZHAO,（西安交通大)
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Eddy Current Testing signals of the transmission/receiver (TR) type probe can be influenced by the directivity of the probe. In the previous study, ECT signal change due to scanning angle was evaluated in ferromagnetic material using a TR type probe, but the mechanism of the change is still not clear. In this study, ECT is conducted changing the orientation of the TR probe both on carbon steel and on austenitic stainless steel, to investigate the mechanism. The results show that the directivity of the probe...
第16回
Options for Using an ASTM E900-15-Style Function to Represent Trend in Domestic RPV Surveillance Data
著者:
Mark KIRK,橋本 資教,野本 明義,（電中研）
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Between 2010 and 2015 the American Society of Testing and Materials (ASTM) developed a new embrittlement trend curve (ETC) to represent trends in a large international collection of reactor pressure vessel (RPV) surveillance data. This work was concluded in 2015 and resulted in an update to the ASTM Standard E900. In this paper we explore options for using an E900-15 style fitting function to represent trends in surveillance data collected from Japanese nuclear power plants....
英字タイトル:
Options for Using an ASTM E900-15-Style Function to Represent Trend in Domestic RPV Surveillance Data
第16回
PD資格試験実施から13年の実施状況
著者:
渡辺 恵司,東海林 一,（電中研）
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The PD Center of Central Research Institute of Electric Power Industry (CRIEPI) commenced performance demonstration examinations (PD examination) for flaw depth sizing of austenitic stainless steel pipes in March 2006. At the end of FY 2018, 50 examination sessions had been completed and 68 candidates had passed the examination. The total number of PD examinee including re-examination and re-certification was 116. Passed candidates can perform depth sizing of SCC flaws with a high level of accuracy. Mean of...
英字タイトル:
Current status of Japanese PD examination for 13 years
第16回
PRAの改善に係る四国電力の取り組みと安全性向上評価について
著者:
堀田 宏司,仁井田 啓志,松永 晃治,西村 幹郎,（四国電力）
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Shikoku Electric Power Co. is making efforts to introduce Risk-Informed Decision Making (RIDM) aiming at continuous improvement of safety not limited to the regulatory framework. As an effort to improve Probabilistic Risk Assessment (PRA) to be utilized in RIDM, we implement “Ikata Unit 3 Project “and are promoting enhancement of PRA. In addition, we submitted Safety Analysis Report and announced the safety improvement activities we are working on....
英字タイトル:
Shikoku Electric Power's efforts to improve PRA and Safety Improvement Assessment
第16回
PRA技術の改善に係る東北電力の取り組みについて
著者:
高橋 利昌,佐藤 大輔,松藤 芳宏,田中 晃,益田 真之介,錦見 篤志,小林 重継,（東北電力）
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Tohoku Electric Power Co., Ltd. plans to continuously improve its safety, based on high-quality risk management. Tn the risk management framework, quantification of risk by PRA plays an important role. Here, we introduce the status of our efforts to improve our PRA method, such as refined internal event level l PRA models, improved data, and the expanded scope of PRA....
英字タイトル:
Tohoku Electric Power's efforts to improve PRA method
第16回
PWRプラントにおける最近の被ばく低減に関する取り組みについて
著者:
山﨑 慎吾,前田 哲宏,石原 伸夫,（三菱重工）,長嶺 邦孝,（ニュークリアデベロップメント）
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The zinc injection has been applied to the Japanese PWR plants for reduction of dose rate of main equipment into the middle of the 2000s. As a result, the dose rate of main equipment was reduced about 40%. In addition to the zinc injection, new measure to reduce of dose rate is demanded. We note the primary water radiation changes significantly, even when water quality and a plant operation parameter are similar value. It is introduced that the approach for identifying the unexplained radiation factor....
英字タイトル:
The approach about the reduction of dose rate in Japanese PWR Plants
第16回
PWR廃止措置における炉内サンプリング工事について
著者:
永田 亮,新田 義一,橋本 達矢,池谷 俊志,森川 玲於奈,鬼塚 博徳,南山 彰男,野田 雅紀,（三菱重工）
発刊日:
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Mihama Unit 1 & 2 are the first decommissioned nuclear power plants in the Japanese PWR (Pressurized Water Reactor). Internal reactor vessel sampling in PWR has never been conducted in Japan before. Mihama Unit 1 & 2 is the first one in the Japanese PWR. Usually, radioactive concentration on nuclear power plant is estimated based on operation history. Decommissioned nuclear power plants are demanded verification between estimation of radioactive concentration and measured result. This dissertation is descri...
英字タイトル:
The nation’s sampling of internal reactor vessel on PWR decommissioning
第16回
ROP制度の本格運用に備えるための過去の不適合事例に学ぶCAP活動の実践
著者:
奈良林 直（東工大）
発刊日:
公開日:
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