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.
充气服是一种个人防护装备，通过软管提供净化空气，保护工人免受辐射污染和内部暴露。在日本原子能机构(Japan Atomic Energy Agency)的核燃料循环工程实验室(Nuclear Fuel Cycle Engineering Laboratories)，这种防护服是用来保护工作人员在缩小和拆除放射性手套箱和设备时免受辐射伤害的，这些设备尤其受到钚的污染。虽然诉讼在类似活动中被广泛采用，但由于诉讼本身及其补充制度的局限性，仍然存在潜在的风险。事实上，在拆除活动中，我们遇到了一些关于这些限制方面的意外事件。为了解决这些潜在的故障，我们采取了各种措施和改进措施，以加强工人的安全。相关的示例包括将软管交换为在弯曲时不会变平的软管，部署空气压缩机来馈送冷冻空气，以及安装供气的监控系统。我们描述了空气补给服系统的缺点和关于我们实现的积极反馈。
{"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}
{"title":"Sorption and Desorption of 3He, Hydrogen and Air Mixture by Activated Charcoal Cooled to 25 K","authors":"T. Norimatsu, K. Yamanoi, Kazuki Sakai","doi":"10.3327/taesj.j21.007","DOIUrl":"https://doi.org/10.3327/taesj.j21.007","url":null,"abstract":"","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":"69437735","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 a Hybrid Connecting Calculational Function for Skyshine Doses in PHITS","authors":"S. Goko, K. Niita","doi":"10.3327/taesj.j21.019","DOIUrl":"https://doi.org/10.3327/taesj.j21.019","url":null,"abstract":"","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":"69437839","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":"Application of Generalized Failure Mechanism Knowledge to Reprocessing Plant for Supporting Maintenance Activity","authors":"Yuuya Yasuda, Makoto Takahashi","doi":"10.3327/taesj.j21.012","DOIUrl":"https://doi.org/10.3327/taesj.j21.012","url":null,"abstract":"","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":"69437801","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}
Naoki Hirokawa, A. Yamaguchi, T. Takata, Sunghyon Jang
{"title":"Qualitative Risk Analysis of Primary Containment Vessel Venting using STAMP/STPA","authors":"Naoki Hirokawa, A. Yamaguchi, T. Takata, Sunghyon Jang","doi":"10.3327/taesj.j21.018","DOIUrl":"https://doi.org/10.3327/taesj.j21.018","url":null,"abstract":"","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":"69437830","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":"Validation of New Fission Yield by Analysis of Post-irradiation Examination in LWR","authors":"A. Iso, S. Takeda, T. Kitada","doi":"10.3327/taesj.j20.028","DOIUrl":"https://doi.org/10.3327/taesj.j20.028","url":null,"abstract":"","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":"69437586","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}
H. Fujiyoshi, M. Ishii, Y. Isobe, Takatoshi Kawashima, Tadashi Magari, Takashi Ikeda, Yukari Fuke, Masato Omoto
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.
{"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}
{"title":"Comparison of Support Contents of External Support Facility for Nuclear Power Plant among Countries","authors":"Ryota Moriyama, S. Takeda, T. Kitada","doi":"10.3327/taesj.j21.011","DOIUrl":"https://doi.org/10.3327/taesj.j21.011","url":null,"abstract":"","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"36 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437795","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}
Naoki Hirokawa, A. Yamaguchi, T. Takata, T. Narukawa
{"title":"Method of Analyzing Criteria for Primary Containment Vessel Venting and Protective Measures for Public Risk Reduction","authors":"Naoki Hirokawa, A. Yamaguchi, T. Takata, T. Narukawa","doi":"10.3327/taesj.j22.003","DOIUrl":"https://doi.org/10.3327/taesj.j22.003","url":null,"abstract":"","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"15 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437902","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}
I. Yamamoto, M. Kawaguchi, S. Miyahara, Masayoshi Uno
{"title":"Thermodynamic Stability of Volatile Radionuclides in Cladding Failure Accident of Sodium-cooled Fast Reactor","authors":"I. Yamamoto, M. Kawaguchi, S. Miyahara, Masayoshi Uno","doi":"10.3327/taesj.j21.024","DOIUrl":"https://doi.org/10.3327/taesj.j21.024","url":null,"abstract":"","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":"69437858","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}
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