{"title":"Gamma-ray Spectra and Dose Measurement Results on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3","authors":"Naoki Mukaida","doi":"10.3327/jaesjb.59.1_21","DOIUrl":"https://doi.org/10.3327/jaesjb.59.1_21","url":null,"abstract":"1. 目的 福島第一原子力発電所3号機の使用済燃料プールからの燃料取り出し作業の実施に向けて、原子炉建屋 オペレーティングフロア(以下「オペフロ」という)は、100mSv/h 以上の高線量の放射線環境であるた め、被ばく低減対策が不可欠である。オペフロにおける作業環境線量の低減は、除染や遮へいが考えられ るが、有効な線量低減対策を講じるためには、方向性線量とγ線エネルギー分布に基づいた測定により現 状把握することが重要である。 (1)γ線スペクトル測定 線源の種類や位置を把握した上で有効な線量低減対策を検討するために、以下の事項についてγ線スペ クトル測定で検証する。 1核種の定性 オペフロの主要核種は、Cs-134,Cs-137 と想定しているが、Co-60 等の他核種からの線量寄与を明 らかにして、遮へい時の線量評価条件の妥当性を確認。 2線源位置の推定 線量寄与の主成分がオペフロ表面か建屋内部であるかを、γ線スペクトル形状で推定し、更なるオペ フロ表面除染の必要性を検証。 3遮へい効果の確認 オペフロに設置した遮へい体の有無によるγ線スペクトル形状の違いから、遮へい効果を確認。 (2)6方位線量測定 オペフロ上の線量率を6方位同時に測定し、上下方向、水平方向からの線量寄与を把握することにより、 有人作業エリアの仮設遮へい体(衝立遮へい等)の必要性を確認するとともに、オペフロ上の有人作業の 線量評価(Hp10)データを取得する。 (3)地上における線量率の変化 オペフロ上の線量が地上における線量にどの程度影響を与えているか確認するため、オペフロ上の遮へ い設置前後の線量変化を地上に設置している線量率モニタで確認する。","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82176310","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Dose evaluation of working area on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3","authors":"K. Shirai","doi":"10.3327/jaesjb.59.1_17","DOIUrl":"https://doi.org/10.3327/jaesjb.59.1_17","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83082488","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2016-07-22DOI: 10.6027/9789289333207-3-en
M. Uesaka
It is very time consuming and requires lot of human efforts to answer the queries (as raised in above section) as the data is scattered in different databases for every examination for the session (most of the examinations are conducted twice in a year). Further, the answers given manually may not be accurate. Some of the above queries can be solved by adopting new technologies but some queries the additional data is required. Solving these queries and acquiring new knowledge form examination data will help university, state government, UGC, ministry of human resource and development etc. take correct decisions regards educational policies that will benefit the society.
{"title":"Objective and Scope","authors":"M. Uesaka","doi":"10.6027/9789289333207-3-en","DOIUrl":"https://doi.org/10.6027/9789289333207-3-en","url":null,"abstract":"It is very time consuming and requires lot of human efforts to answer the queries (as raised in above section) as the data is scattered in different databases for every examination for the session (most of the examinations are conducted twice in a year). Further, the answers given manually may not be accurate. Some of the above queries can be solved by adopting new technologies but some queries the additional data is required. Solving these queries and acquiring new knowledge form examination data will help university, state government, UGC, ministry of human resource and development etc. take correct decisions regards educational policies that will benefit the society.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73882879","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy kernel made of YSZ which surrogates PuO2-YSZ have been started in the Japanese fiscal year 2015. As results of ZrC coating tests on YSZ particle by the bromide process developed in Japan Atomic Energy Agency, stoichiometric ZrC coatings with 18 21 μm of thicknesses were obtained with 0.1 kg of particle loading weight. As indicated by a thermochemical analysis on the chemical stability of YSZ against the ZrC bromide process, no deterioration of YSZ exposed by source gases of ZrC bromide process was observed through the characterization by Scanning Transmission Electron Microscope (STEM) observation. Finally, reproducibility of stoichiometric ZrC coating on YSZ particle was demonstrated by the bromide chemical vapor deposition process.
{"title":"Development of Security and Safety Fuel for Pu-burner HTGR","authors":"M. Goto","doi":"10.1115/ICONE25-67110","DOIUrl":"https://doi.org/10.1115/ICONE25-67110","url":null,"abstract":"To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy kernel made of YSZ which surrogates PuO2-YSZ have been started in the Japanese fiscal year 2015. As results of ZrC coating tests on YSZ particle by the bromide process developed in Japan Atomic Energy Agency, stoichiometric ZrC coatings with 18 21 μm of thicknesses were obtained with 0.1 kg of particle loading weight. As indicated by a thermochemical analysis on the chemical stability of YSZ against the ZrC bromide process, no deterioration of YSZ exposed by source gases of ZrC bromide process was observed through the characterization by Scanning Transmission Electron Microscope (STEM) observation. Finally, reproducibility of stoichiometric ZrC coating on YSZ particle was demonstrated by the bromide chemical vapor deposition process.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82314629","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Risk evaluation method for fault displacements by engineering approach","authors":"T. Narabayashi","doi":"10.3327/jaesjb.58.9_542","DOIUrl":"https://doi.org/10.3327/jaesjb.58.9_542","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81264725","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Rubble removal work, Decontamination and Shield installation on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3","authors":"Takashi Inoue","doi":"10.3327/jaesjb.59.1_15","DOIUrl":"https://doi.org/10.3327/jaesjb.59.1_15","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91401587","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2016-07-22DOI: 10.4324/9780203992319-12
Akira Yamaguchi
{"title":"Risk Appraisal and Management","authors":"Akira Yamaguchi","doi":"10.4324/9780203992319-12","DOIUrl":"https://doi.org/10.4324/9780203992319-12","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82278884","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Design and Construction plan of Spent Fuel Removal System for Fukushima Daiichi Nuclear Power Station Unit 3","authors":"F. Shinozaki","doi":"10.3327/jaesjb.59.1_26","DOIUrl":"https://doi.org/10.3327/jaesjb.59.1_26","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79678469","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Development of Security and Safety Fuel for Pu-burner HTGR","authors":"Masaki Honda","doi":"10.1115/ICONE25-67048","DOIUrl":"https://doi.org/10.1115/ICONE25-67048","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73982787","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Seismic Test Result of motor operated valve actuators for Nuclear Power Plant","authors":"N. Kojima","doi":"10.1115/PVP2017-65600","DOIUrl":"https://doi.org/10.1115/PVP2017-65600","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82893148","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：