Transactions of the Atomic Energy Society of Japan最新文献_第2页

Safety Improvements in Air-fed Suit for Workin Plutonium Fuel Facility Decommissioning 工作钚燃料设施退役充气服安全性改进

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j20.035

H. Kikuchi, H. Hirano, A. Kitamura

{"title":"Safety Improvements in Air-fed Suit for Workin Plutonium Fuel Facility Decommissioning","authors":"H. Kikuchi, H. Hirano, A. Kitamura","doi":"10.3327/taesj.j20.035","DOIUrl":"https://doi.org/10.3327/taesj.j20.035","url":null,"abstract":"The air-fed suit is a type of personal protective equipment that provides puriﬁed air through a hose and protects a worker from radiation contamination and internal exposure. In the Nuclear Fuel Cycle Engineering Laboratories of the Japan Atomic Energy Agency, the suit is used to protect a worker from radiation during the size reduction and dismantlement of radioactive gloveboxes and equipment, which are contaminated particularly with plutonium. Although the suit has been widely adopted in similar activities, there still exist potential risks due to the limiting features of the suit it-self and its supplemental system. In fact, we faced several unexpected events regarding such restrict-ed aspects during dismantling activities. To address these failure potentials, we have implemented various countermeasures and improvements to enhance worker safety. Relevant examples include the exchange of the hose to one that is free from ﬂattening while bending, the deployment of an air com pressor to feed chilled air, and the installation of a monitoring system of the supplied air. We describe the disadvantages of the air-fed suit system and positive feedback regarding our implementations.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437655","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

Sorption and Desorption of 3He, Hydrogen and Air Mixture by Activated Charcoal Cooled to 25 K 活性炭对3He，氢气和空气混合物的吸附和解吸

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.007

T. Norimatsu, K. Yamanoi, Kazuki Sakai

引用次数: 0

Development of a Hybrid Connecting Calculational Function for Skyshine Doses in PHITS PHITS中日照剂量混合连接计算函数的建立

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.019

S. Goko, K. Niita

引用次数: 0

Application of Generalized Failure Mechanism Knowledge to Reprocessing Plant for Supporting Maintenance Activity 广义失效机理知识在后处理设备维修支持中的应用

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.012

Yuuya Yasuda, Makoto Takahashi

引用次数: 0

Qualitative Risk Analysis of Primary Containment Vessel Venting using STAMP/STPA 使用STAMP/STPA对主安全壳排气进行定性风险分析

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.018

Naoki Hirokawa, A. Yamaguchi, T. Takata, Sunghyon Jang

引用次数: 0

Validation of New Fission Yield by Analysis of Post-irradiation Examination in LWR 用小水堆辐照后检验分析验证新的裂变产额

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j20.028

A. Iso, S. Takeda, T. Kitada

引用次数: 0

Fundamental study on a diagnostic technology for degradations of cable insulation materials due to radiation exposure and aging 电缆绝缘材料辐射老化退化诊断技术的基础研究

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.010

H. Fujiyoshi, M. Ishii, Y. Isobe, Takatoshi Kawashima, Tadashi Magari, Takashi Ikeda, Yukari Fuke, Masato Omoto

{"title":"Fundamental study on a diagnostic technology for degradations of cable insulation materials due to radiation exposure and aging","authors":"H. Fujiyoshi, M. Ishii, Y. Isobe, Takatoshi Kawashima, Tadashi Magari, Takashi Ikeda, Yukari Fuke, Masato Omoto","doi":"10.3327/taesj.j21.010","DOIUrl":"https://doi.org/10.3327/taesj.j21.010","url":null,"abstract":"Age-related degradations of various cables used in nuclear power plants have been of constant concern. In general, many types of polymer material are selected for cable insulators because of their high insulating performance. However, they are degraded in not only their mechanical performance but also their electric performance by radiation exposure. Since current inspection methods, such as measuring the insulation resistance, require substantially high costs and workloads, simpli ﬁ ed nondestructive methods will be useful. We have developed a digital hammering inspection system with an AE ( acoustic emission ) sensor. This system detects the degradations of cable insulators due to radiation exposure and aging by assessing the frequency distributions obtained by FFT ( fast Fourier transform ) analysis of measured signals. In this study, we evaluated the relationship between the natural frequency obtained by the digital hammering system and the breaking elongation measured by the tensile testing of the insulating materials after electron beam irradiations of up to a maximum of 2,000kGy for cables including those used in a nuclear power plant for about 30 years.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437789","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: 0

Comparison of Support Contents of External Support Facility for Nuclear Power Plant among Countries 各国核电厂外部支持设施支持内容比较

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.011

Ryota Moriyama, S. Takeda, T. Kitada

引用次数: 0

Method of Analyzing Criteria for Primary Containment Vessel Venting and Protective Measures for Public Risk Reduction 降低公共风险的初级安全壳通风标准及防护措施分析方法

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j22.003

Naoki Hirokawa, A. Yamaguchi, T. Takata, T. Narukawa

引用次数: 0

Thermodynamic Stability of Volatile Radionuclides in Cladding Failure Accident of Sodium-cooled Fast Reactor 钠冷快堆包壳失效事故中挥发性放射性核素的热力学稳定性

Transactions of the Atomic Energy Society of Japan Pub Date : 2022-01-01 DOI: 10.3327/taesj.j21.024

I. Yamamoto, M. Kawaguchi, S. Miyahara, Masayoshi Uno

引用次数: 0