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第11回
AREVA?fs Filtered Containment Venting System (FCVS) Basic Design, Performance and Verification Test of FCVS for BWRs
著者:
ノーベルト　ロッシュ,Norbert LOSCH,セバスタイン ブールマン,Sebastian BUHLMANN ,クリスチャン　ヒュッタラー,Christian HUTTERER,クリストフ　スティパニー,Christoph STIEPANI, 戸塚　文夫,Fumio TOTSUKA,塚原　達也,Tatsuya TSUKAHARA,細見　健二,Kenji HOSOMI
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After the great earthquake and a tsunami as consequence March 11, 2011, a severe accident happened at nuclear power plant Fukushima Daiichi. The severe accident lead to core damage and containment failure and finally to large release of radioactive substances to the environment. As part of the severe accident management and to reinforce the mitigation concepts against a containment failure, the Filtered Containment Venting System (FCVS) will be introduced at Japanese nuclear power plants, to have a pos...
英字タイトル:
AREVA?fs Filtered Containment Venting System (FCVS) Basic Design, Performance and Verification Test of FCVS for BWRs
第11回
Correlation between phosphorus segregation and stress corrosion cracking susceptibility in the heat affected zone of an A533B-A182 dissimilar weld joint
著者:
Ziqing ZHAI,Hiroshi ABE,Yuichi MIYAHARA,Yutaka WATANABE
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Effects of thermal history and segregation on the susceptibility of stress corrosion cracking (SCC) in the heat-affected zone (HAZ) of an alloy 182-A533B dissimilar weld joint in high temperature, oxygenated water doped with SO4 2- and Cl- was evaluated by creviced bent beam test. Results indicate that step cooling and the addition of Cl- promoted SCC propagation and reactivation in HAZ. It is also suggested that compositional changes induced by welding and step cooling, especially the segregation of ph...
英字タイトル:
Correlation between phosphorus segregation and stress corrosion cracking susceptibility in the heat affected zone of an A533B-A182 dissimilar weld joint
第11回
Effects of thermal history and microstructure on grain boundary segregation in the heat-affected zone of an Alloy182-A533B dissimilar weld joint
著者:
Ziqing ZHAI ,Yuichi MIYAHARA,Hiroshi ABE ,Yutaka WATANABE
発刊日:
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Grain boundary (GB) segregation of phosphorus and alloying elements in the heat-affected zone (HAZ) of an Alloy182- A533B dissimilar weld joint used in nuclear reactor pressure vessels was studied quantitatively by three-dimensional atom probe tomography. Non-equilibrium segregation occurred during welding and post-weld heat treatment, leading to remarkable enrichment of P, C, Mn and Mo at GBs, of which the levels were all microstructure- dependent. After step cooling, P and Mn showed further increase ...
英字タイトル:
Effects of thermal history and microstructure on grain boundary segregation in the heat-affected zone of an Alloy182-A533B dissimilar weld joint
第11回
Image Enhancement for Concrete Bridge Inspection with Portable 950 keV/ 3.95 MeV X-ray Source
著者:
Cuixiang Pei, Mitsuru Ueaska, Wenjing Wu , Katsuhiro Dobashi, Takeshi Fujiwara, Jyoichi, Jyoichi Kusano, Naoki Nakamura, and Yositomi Kimura
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Abstract: The use of portable and high-energy x-ray system can provide a very promising approach for the inspection of aged concrete structures. However, due to the effect of large scattering of low-energy x-ray in a thick concrete, the noise properties and contrast of the radiographic images need to be optimized to ensure reliable interpretation. Therefore, in order to improve the inspection ability, an image denoising method with the combination of wavelet and curvelet transform and image contrast e...
英字タイトル:
Image Enhancement for Concrete Bridge Inspection with Portable 950 keV/ 3.95 MeV X-ray Source
第11回
Reliability evaluation of Fatigue crack signal in austenite stainless steels 佐藤 打美亥 Dummy SATOU
著者:
Hao FENG,Ryoichi URAYAMA,Tetsuya UCHIMOTO,Toshiyuki TAKAGI
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Abstract..This paper investigates the influence of machining process on eddy current signals of fatigue cracks in low carbon austenite stainless steels. Several fatigue cracks are created using four point bending method. The grinding process on crack mouth after the formation of fatigue crack seals the crack and gives certain amount of conductivity. This phenomenon on fatigue cracks is confirmed through comparison with the numerical simulation of ECT signals. ...
英字タイトル:
Reliability evaluation of Fatigue crack signal in austenite stainless steels 佐藤 打美亥 Dummy SATOU
第11回
2次元検出器方式による cosα法を用いた残留応力測定手法について
著者:
野末 秀和,Hidekazu NOZUE,内山 宗久,Munehisa UCHIYAMA,加藤 達也,Tatsuya KATO,渕上 静也,Seiya FUCHIGAMI
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The on-site residual stress measurement by the conventional XRD method is difficult because of the size of the equipment. For mainly on-site measurement and also u sing in the production line, we have developed the portable x-ray residual stress analyzer which is compact size e and short measurement time. The analyzer is usin cosα method, not sin2psi method which is used for conventional XRD stress measurement, and measure the stress from the complete Debye ring information by single a le X-ray exposure. I...
英字タイトル:
For residual stress measurement method using a cosα method by the two-dimensional detector system
第11回
AE センサを用いたケミカルアンカの非破壊検査技術の開発 (1) 実験的検討
著者:
江藤 淳二,Junji ETOH,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,礒部 仁博,Yoshihiro ISOBE
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Post-installed adhesive anchor bolts are commonly used on all types projects, from standard buildings to bridges and nuclear power plants. They are exposed to varying and diverse environmental conditions which are significant successfully to make connections to concrete structures for many years. In order to maintain the safety and reliability of concrete structures such as buildings or bridges on higher level over a long period time, we developed a new non-destructive inspection system of adhesive an...
英字タイトル:
Development of non-destructive inspection technique for adhesive anchor bolts using AE sensor (1) An experimental approach
第11回
AE センサを用いたケミカルアンカの非破壊検査技術の開発 (2) 理論的検討
著者:
小川 良太,Ryota OGAWA,江藤 淳二,Junji ETOH,松永 嵩,Takashi MATSUNAGA,礒部 仁博,Yoshihiro ISOBE
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We have developed a non-destructive inspection technique using the AE (acoustic em sion) sensor. It is intended to be non-destructive evaluation in soundness of the adhesion anchor is installed in a nuclear power plant. We analyzed the Eigen frequ cy of the adhesive anchor measured by the AE sensor using a finite element method . Results of the analysis of the Eigen frequency, the change in Eigen frequency cou ld be confirmed between the adhesive anchor which simulates the Peeling of the resi n by aging de...
英字タイトル:
Development of non-destructive inspection technique for adhesive anchor bolts using AE sensor (2) Theoretical examination
第11回
BWR 模擬環境での SCC 試験のためのすき間形成材の評価
著者:
阿部 博志,Hiroshi ABE,石倉 潤一,Junichi ISHIKURA,渡邉 豊,Yutaka WATANABE
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The crevice former which does not release anion impurities (e.g. Cl-) for SCC (Stress Corrosion Cracking) initiation experiment in simulated boiling water reactor water environment has been ev aluated. The creviced bent beam tests of sensitized stainless steel with using the crevice condition as an experimental parameter were carried out. Even SCC occurred at the part of specimen su rface which tested with only the spacer (no crevice former), it has been difficult to obtain the reproducible result. SCC ini...
英字タイトル:
Evaluation of crevice former for SCC initiation experiment in simulated BWR water environment
第11回
BWR 炉内構造物等点検評価ガイドライン 炉心シュラウドの改訂方針
著者:
三橋 忠浩,Tadahiro MITSUHASHI,江波戸 翔一,Shoichi EBATO,藤野 拓史,Takushi FUJINO,吉田 伸司,Shinji YOSHIDA
発刊日:
公開日:
2.ガイドラインの概要 本ガイドラインは、点検対象(基本的な考え方及び点 検対象部位)、点検(点検方法及び点検周期)、評価で構 成されている。本項では、各構成について第 4 版での記 載内容の概要を報告する。炉内構造物等点検評価ガイド ライン[炉心シュラウド]は、平成 13 年 11 月に初版が 発行された後、平成 16 年 9 月に第 2 版が、平成 19 年 4 月に第3版が、平成20年6月に第4版が発行された。 初版では、炉心シュラウドの点検方法、点検周期、評 価の考えが示された。第 2 版では、点......
英字タイトル:
Guideline for BWR Inspection Program Direction to revise Guideline for Core Shroud
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