scienti fi c and technological policy. In this process, OPECST holds public hearings and gathers opinions from various participants: experts, industry, citizens, and so on. It held many public hearings and assessments on nuclear energy policy in the 1990s, when French people started to demand more transparency and independence of the nuclear safety regime than before. So we can assume that OPECST helped the reform in the 1990s and in the 2000s that fi nally established the Law on Transparency and Security in the Nuclear Field. This research aims to precisely clarify its function through a survey of all the reports of OPECST on nuclear safety policy published in this period and of political decisions related to them. As a result, it is shown that the function of OPECST consists of three elements: it de fi nes problems, elaborates policy recommendations from various opinions, and accumulates its survey results in the form of reports. Nowadays, the form of the discussion carried out by OPECST is changing, so we have to learn both its history and recent activities to make a policy-making system that would be suitable in Japan.
{"title":"Role of the French Parliamentary Office in Changing Nuclear Energy Policy","authors":"K. Kimura, H. Kimura","doi":"10.3327/TAESJ.J17.011","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.011","url":null,"abstract":"scienti fi c and technological policy. In this process, OPECST holds public hearings and gathers opinions from various participants: experts, industry, citizens, and so on. It held many public hearings and assessments on nuclear energy policy in the 1990s, when French people started to demand more transparency and independence of the nuclear safety regime than before. So we can assume that OPECST helped the reform in the 1990s and in the 2000s that fi nally established the Law on Transparency and Security in the Nuclear Field. This research aims to precisely clarify its function through a survey of all the reports of OPECST on nuclear safety policy published in this period and of political decisions related to them. As a result, it is shown that the function of OPECST consists of three elements: it de fi nes problems, elaborates policy recommendations from various opinions, and accumulates its survey results in the form of reports. Nowadays, the form of the discussion carried out by OPECST is changing, so we have to learn both its history and recent activities to make a policy-making system that would be suitable in Japan.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90760213","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}
Indirect neutron radiography by transferring radiation from an activated metal foil to a film is an effective technique under a high gamma-ray field. By adopting an X-ray imaging plate (IP), the sensitivity characteristics of indirect neutron radiography were quantitatively evaluated through experiments using cyclotron accelerator neutrons. The wider dynamic range and higher sensitivity of the IP method than the conventional film method were shown through parametric tests of neutron flux, exposure time, and transfer time. It was confirmed that the X-ray IP-based transfer exposure method is a promising neutron radiography method under neutron/gamma mixed fields.
{"title":"Neutron Radiography Characteristics of Transfer Exposure Method Using X-ray Imaging Plate","authors":"Hiroyuki Uno, Ryuji Uemoto, K. Nittoh, Shiro Sogabe, Yukio Sonoda, Masatoshi Kawashima","doi":"10.3327/TAESJ.J17.002","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.002","url":null,"abstract":"Indirect neutron radiography by transferring radiation from an activated metal foil to a film is an effective technique under a high gamma-ray field. By adopting an X-ray imaging plate (IP), the sensitivity characteristics of indirect neutron radiography were quantitatively evaluated through experiments using cyclotron accelerator neutrons. The wider dynamic range and higher sensitivity of the IP method than the conventional film method were shown through parametric tests of neutron flux, exposure time, and transfer time. It was confirmed that the X-ray IP-based transfer exposure method is a promising neutron radiography method under neutron/gamma mixed fields.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77254937","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. Sakamoto, Y. Akagi, Kazuo Yamada, Y. Tachi, Daisuke Fukuda, Koichi Ishimatsu, M. Matsuda, Nozomi Saito, Jitsuya Uemura, T. Namihira, M. Shigeishi
Concrete debris contaminated with radioactive cesium and other nuclides has been generated by the accident in the Fukushima Dai-ichi nuclear power plant. Moreover, there is concern that a large amount of radioactive concrete waste will be generated by the decommissioning of nuclear power plants in the future. Although conventional techniques are effective in decontaminating concrete with flat surfaces such as floors and walls, it is not clear what techniques to apply for decontaminating radioactive concrete debris. In this study, focusing on a pulsed power discharge technique, fundamental experimental work was carried out and the applicability of the technique to decontaminating radioactive concrete debris associated with the accident in the Fukushima Dai-ichi nuclear power plant was evaluated. The decontamination of concrete by applying the aggregate recycling technique using the pulsed power discharge technique was evaluated by measuring the radioactivity concentration of the divided aggregate and sludge from the contaminated concrete using a Ge-semiconductor detector. It indicated a reduction of the radioactivity concentration in the recovered aggregate and an increase in the radioactivity concentration in the sludge. These findings suggest that the division of the contaminated concrete debris into aggregate and sludge could result in the decontamination and reuse of the aggregate, which would reduce the amount of contaminated concrete debris.
{"title":"Decontamination of Radioactive Concrete Waste and Reuse of Aggregate Using Pulsed Power Technology","authors":"H. Sakamoto, Y. Akagi, Kazuo Yamada, Y. Tachi, Daisuke Fukuda, Koichi Ishimatsu, M. Matsuda, Nozomi Saito, Jitsuya Uemura, T. Namihira, M. Shigeishi","doi":"10.3327/TAESJ.J16.037","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.037","url":null,"abstract":"Concrete debris contaminated with radioactive cesium and other nuclides has been generated by the accident in the Fukushima Dai-ichi nuclear power plant. Moreover, there is concern that a large amount of radioactive concrete waste will be generated by the decommissioning of nuclear power plants in the future. Although conventional techniques are effective in decontaminating concrete with flat surfaces such as floors and walls, it is not clear what techniques to apply for decontaminating radioactive concrete debris. In this study, focusing on a pulsed power discharge technique, fundamental experimental work was carried out and the applicability of the technique to decontaminating radioactive concrete debris associated with the accident in the Fukushima Dai-ichi nuclear power plant was evaluated. The decontamination of concrete by applying the aggregate recycling technique using the pulsed power discharge technique was evaluated by measuring the radioactivity concentration of the divided aggregate and sludge from the contaminated concrete using a Ge-semiconductor detector. It indicated a reduction of the radioactivity concentration in the recovered aggregate and an increase in the radioactivity concentration in the sludge. These findings suggest that the division of the contaminated concrete debris into aggregate and sludge could result in the decontamination and reuse of the aggregate, which would reduce the amount of contaminated concrete debris.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72732348","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}
The Periodic Safety Review （ PSR ） is a continuous safety enhancement process to improve overall plant safety. The report on the Fukushima Daiichi accident issued by the IAEA indicated that the ap-proach to PSR in Japan was not fully in line with guidance from the IAEA. PSR was originally an ef fi cient means of improving the safety level of installations, and to make a decision on the continuation of the reactor operation for the next decade. In order to achieve the objectives of PSR, plant operators need to review their operating experience as well as reassess their past review and identify fi ndings which lead to improvements of plant safety. It is also important that regulators participate in the pre-paratory work of the review to identify the issues and the outcome of the review. To improve the ef fi ciency and effectiveness of this activity, the regulators need to develop a technical information base re fl ecting the safety inspection carried at the sites to identify issues. The plant operator also needs to reassess the past PSR to verify the validity of the review. Regulators and plant operators should con-tinue to make bilateral efforts through PSR and deliver improvements of safety throughout the plant life.
{"title":"A Study on Enhancing the Effectiveness of Periodic Safety Review of Nuclear Power Plants","authors":"A. Yamamoto, N. Sekimura","doi":"10.3327/TAESJ.J16.038","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.038","url":null,"abstract":"The Periodic Safety Review （ PSR ） is a continuous safety enhancement process to improve overall plant safety. The report on the Fukushima Daiichi accident issued by the IAEA indicated that the ap-proach to PSR in Japan was not fully in line with guidance from the IAEA. PSR was originally an ef fi cient means of improving the safety level of installations, and to make a decision on the continuation of the reactor operation for the next decade. In order to achieve the objectives of PSR, plant operators need to review their operating experience as well as reassess their past review and identify fi ndings which lead to improvements of plant safety. It is also important that regulators participate in the pre-paratory work of the review to identify the issues and the outcome of the review. To improve the ef fi ciency and effectiveness of this activity, the regulators need to develop a technical information base re fl ecting the safety inspection carried at the sites to identify issues. The plant operator also needs to reassess the past PSR to verify the validity of the review. Regulators and plant operators should con-tinue to make bilateral efforts through PSR and deliver improvements of safety throughout the plant life.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80081872","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}
Four of premises decontamination. for attenuation by consid-eration of the radioactive half-lives of 134 Cs and 137 Cs to compensate the time gap between the sur-veyed dates. Measuring points were categorized by an index of a pair of indoor positions and the height from the fl oor as well as outdoor positions and the height from the ground. The observed differ-ences among the dose rates under this categorization, for example, the rate on the second fl oor is lower than that of the ceiling of the fi rst fl oor, qualitatively agree with the reported results of simulations, suggesting that some assumptions used by the simulations coincide reasonably well with actual condi-tions. The observed ratio of the doses inside and outside of wooden houses also essentially agrees with the reported ratio measured by different methods in different cities. The ratio has been con fi rmed to decrease with increasing open air dose rate when the open air dose rate is less than 0.5 μ Sv / h.
{"title":"Measurement Example of Radiation Dose Rate in Private Premises Contaminated by the Fukushima Nuclear Power Plant Accident","authors":"Kunio Ito","doi":"10.3327/TAESJ.J17.003","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.003","url":null,"abstract":"Four of premises decontamination. for attenuation by consid-eration of the radioactive half-lives of 134 Cs and 137 Cs to compensate the time gap between the sur-veyed dates. Measuring points were categorized by an index of a pair of indoor positions and the height from the fl oor as well as outdoor positions and the height from the ground. The observed differ-ences among the dose rates under this categorization, for example, the rate on the second fl oor is lower than that of the ceiling of the fi rst fl oor, qualitatively agree with the reported results of simulations, suggesting that some assumptions used by the simulations coincide reasonably well with actual condi-tions. The observed ratio of the doses inside and outside of wooden houses also essentially agrees with the reported ratio measured by different methods in different cities. The ratio has been con fi rmed to decrease with increasing open air dose rate when the open air dose rate is less than 0.5 μ Sv / h.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86278494","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}
S. Tsuda, M. Tanigaki, Tadayoshi Yoshida, R. Okumura, Kimiaki Saito
Ambient dose equivalent （ H ＊ （ 10 ）） rates in the environment in Fukushima prefecture were measured by NaI （ Tl ） and CsI （ Tl ） scintillation detectors whose crystal shapes are different. The indicated values of H ＊ （ 10 ） measured by a CsI （ Tl ） scintillation detector with a rectangular parallelepiped crystal （ 13 × 13 × 20 mm 3 ） were approximately 40 ％ higher than those of a CsI （ Tl ） scintillation detector with a rectangular parallelepiped crystal （ 38 × 38 × 25 mm 3 ） and 20 ％ higher than those of a NaI （ Tl ） scintillation detector with a cylindrical crystal （ 25.4 mm in diameter and height ） in the case where G （ E ） functions were used in parallel irradiation geometry. It was found that cylindrical crystals are more appropriate than rectangular parallelepiped crystals with respect to directional dependence in environmental dose rate monitoring. However, using a spectrum-dose conversion operator determined in a rotational irradiation geometry, the values of H ＊ （ 10 ） agreed within 10 ％ among all the detectors. These results indicate that the directional dependence of scintillation detectors should be carefully considered for H ＊ （ 10 ） dose rate monitoring in the environment.
{"title":"Dependence of dose rate measurement in the environment on crystal configuration of scintillation detectors","authors":"S. Tsuda, M. Tanigaki, Tadayoshi Yoshida, R. Okumura, Kimiaki Saito","doi":"10.3327/TAESJ.J16.039","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.039","url":null,"abstract":"Ambient dose equivalent （ H ＊ （ 10 ）） rates in the environment in Fukushima prefecture were measured by NaI （ Tl ） and CsI （ Tl ） scintillation detectors whose crystal shapes are different. The indicated values of H ＊ （ 10 ） measured by a CsI （ Tl ） scintillation detector with a rectangular parallelepiped crystal （ 13 × 13 × 20 mm 3 ） were approximately 40 ％ higher than those of a CsI （ Tl ） scintillation detector with a rectangular parallelepiped crystal （ 38 × 38 × 25 mm 3 ） and 20 ％ higher than those of a NaI （ Tl ） scintillation detector with a cylindrical crystal （ 25.4 mm in diameter and height ） in the case where G （ E ） functions were used in parallel irradiation geometry. It was found that cylindrical crystals are more appropriate than rectangular parallelepiped crystals with respect to directional dependence in environmental dose rate monitoring. However, using a spectrum-dose conversion operator determined in a rotational irradiation geometry, the values of H ＊ （ 10 ） agreed within 10 ％ among all the detectors. These results indicate that the directional dependence of scintillation detectors should be carefully considered for H ＊ （ 10 ） dose rate monitoring in the environment.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2018-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81436231","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":"Current Status on First Principles Calculation and its Progress of Application on Nuclear Energy Field","authors":"M. Machida","doi":"10.3327/jaesjb.60.9_552","DOIUrl":"https://doi.org/10.3327/jaesjb.60.9_552","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86162680","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":"三次元中性子輸送・燃焼計算に基づくBWR使用済燃料内の中性子源核種242Cm・244Cm組成および中性子放出率の分布","authors":"大貴 渡辺, 高範 亀山","doi":"10.3327/TAESJ.J16.020","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.020","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89291782","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":"抽出剤–［C2mim］［Tf2N］混合相を用いた協同効果を伴う燃料デブリ由来の放射性核種の抽出挙動の基礎研究","authors":"Yuji Yada, T. Arai","doi":"10.3327/TAESJ.J16.025","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.025","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82754986","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 : 2017-01-23DOI: 10.1051/EPJCONF/20159306001
A. Kimura
Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program" in Japan at October 2013. The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the team aims at improving the accuracy of the data. The background and research plan of the AIMAC project are presented.
{"title":"R&D for accuracy improvement of neutron nuclear data on minor actinides","authors":"A. Kimura","doi":"10.1051/EPJCONF/20159306001","DOIUrl":"https://doi.org/10.1051/EPJCONF/20159306001","url":null,"abstract":"Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as \"Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)\" has been started as one of the \"Innovative Nuclear Research and Development Program\" in Japan at October 2013. The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the team aims at improving the accuracy of the data. The background and research plan of the AIMAC project are presented.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91056184","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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