Atomic Energy Society of Japan最新文献_第7页

Gamma-ray Spectra and Dose Measurement Results on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组反应堆建筑换料层伽玛能谱及剂量测量结果

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.59.1_21

Naoki Mukaida

{"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":"56 1","pages":""},"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}

引用次数: 2

Dose evaluation of working area on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组反应堆厂房换料层工作区域剂量评估

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.59.1_17

K. Shirai

引用次数: 1

Objective and Scope 目标及范围

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.6027/9789289333207-3-en

M. Uesaka

引用次数: 0

Development of Security and Safety Fuel for Pu-burner HTGR 钚燃烧器HTGR安全与安全燃料的研制

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.1115/ICONE25-67110

M. Goto

{"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":"36 1","pages":""},"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}

引用次数: 1

Risk evaluation method for fault displacements by engineering approach 基于工程方法的断层位移风险评价方法

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.58.9_542

T. Narabayashi

引用次数: 0

Rubble removal work, Decontamination and Shield installation on the Reactor Building Refueling Floor of Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组反应堆建筑换料层的瓦砾清除、净化和防护罩安装工作

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.59.1_15

Takashi Inoue

引用次数: 0

Risk Appraisal and Management 风险评估与管理

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.4324/9780203992319-12

Akira Yamaguchi

引用次数: 1

Design and Construction plan of Spent Fuel Removal System for Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组乏燃料清除系统设计与施工方案

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.3327/jaesjb.59.1_26

F. Shinozaki

引用次数: 0

Development of Security and Safety Fuel for Pu-burner HTGR 钚燃烧器HTGR安全与安全燃料的研制

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.1115/ICONE25-67048

Masaki Honda

引用次数: 0

Seismic Test Result of motor operated valve actuators for Nuclear Power Plant 核电站电动阀门执行器的抗震试验结果

Atomic Energy Society of Japan Pub Date : 2016-07-22 DOI: 10.1115/PVP2017-65600

N. Kojima

引用次数: 1