第14回
ASRポテンシャル評価のための骨材試験方法に関する評価
著者:
江藤 淳二,Junji ETOH,落合 孝正,Takamasa OCHIAI,小川 彰一,Shoiti OGAWA,渋谷 和俊,Shibuya KAZUTOSHI,丸山 一平,Ippei MARUYAMA,山田 一夫,Kazuo YAMADA,滝沢 真之,Masayuki TAKIZAWA
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Test method has not been maintained for late-expansive aggregates (which cause cracks in concrete after 10 years or more), in addition to the early-expansive aggregates which have been considered as the major cause of ASR in Japan. In order to confirm the effectiveness of the aggregate test method of JNES flow (the method mainly composed of international methods RILEM AAR - 3 and AAR - 4) and to prepare applicable aggregate test method, we conducted comparative tests using domestic and foreign aggregate...
英字タイトル:
Evaluation on Aggregate Testing Method for ASR Potential Evaluation
第15回
コンクリート構造物のASR診断方法に関する評価
著者:
江藤 淳二,(三菱総研),五十嵐 豪,(東北大),小川 彰一,渋谷 和俊,(太平洋コンサルタント),丸山 一平,(名古屋大学),山田 一夫,(国立環境研究所),滝沢 真之,(三菱総合研究所)
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Recently, many concrete structures such as bridge piers of the highway, damaged by Alkali Silica Reaction (ASR) have been observed in Japan. From this background, based on the latest knowledge of domestic and international, the ASR diagnostic method that emphasizes the petrological examination after the core sampling was proposed on Japan Nuclear Energy Safety Organization (JNES) report. In this research, in order to confirm the effectiveness of ASR diagnostic method for concrete structures proposed in JNES...
英字タイトル:
Evaluation on ASR diagnostic method for concrete structures
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15回
軽水炉コンクリート構造物の照射劣化予測手法の開発に係る研究計画
著者:
滝沢 真之,鈴木 清照,江藤 淳二,河合 理城,藤山 翔乃,(三菱総研),丸山 一平,(名古屋大),紺谷 修,澤田 祥平,石川 俊介,(鹿島建設)
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A new research program of irradiation effects on LWR concrete member has been started since 2017. The previous research results indicate the reference level of neutron irradiation degradation on concrete should be set at 1 x 1019 n/cm2 which is one order of magnitude lower than the conventional reference level used in Japan. Several issues remain after the previous research and the objectives for clarifying the issues are set in the new project which is scheduled for five and half years. And international c...
英字タイトル:
The Research Plan on Development of Evaluation Method of LWR Concrete Irradiation Effect
第14回
軽水炉安全ロードマップの高度活用
著者:
滝沢 真之,Masayuki TAKIZAWA
発刊日:
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A roadmap on safety research and human resource cultivation for Light-Water Reactor (LWR) has been developed by a lot of stakeholders, that is experts of government, academia and industry in the committee of Atomic Energy Society of Japan since 2014. In the roadmap, technical, social and policy issues are covered and the issues are categorized into several research fields, e.g. _Design”, _Operation and Maintenance”, _Accident Management”, _Decommissioning”, _Nuclear Security” and so on. A lot of stakeho...
英字タイトル:
Trial for Advanced Application of LWR Safety Roadmap