The Fukushima accident of March 2011 had great political, economic, and social impacts on Japan and marked a very important turning point in Japan’s energy policy. As the accident has also greatly exposed the vulnerability of Japan’s energy security, it is crucial to clarify the path that Japan should take to maintain and secure its energy security in case of any possible future outbreak that may threaten its energy security. For this purpose, we conducted a comprehensive and structural analysis of Japan’s energy security based on APERC’s 4As framework and by using fuzzy logic and the Fuzzy-DEMATEL method to quantitatively understand the performance of Japan’s energy security and how the Fukushima accident had impacted the performance. Our results demonstrate that Japan’s energy security has clearly degraded after experiencing Fukushima accident. In addition, the results of the structural analysis by the Fuzzy-DEMATEL method show that the most salient dimension in the 4As framework for improving Japan’s energy security is the “Availability” dimension, and for this purpose nuclear energy and renewables play very important roles in securing the future energy security in Japan; this is consistent with the current energy policy measures announced in the Strategic Energy Plan of 2014.
{"title":"Quantitative Analysis of Japan’s Energy Security based on Fuzzy Logic","authors":"R. Yamanishi","doi":"10.1155/2017/4865913","DOIUrl":"https://doi.org/10.1155/2017/4865913","url":null,"abstract":"The Fukushima accident of March 2011 had great political, economic, and social impacts on Japan and marked a very important turning point in Japan’s energy policy. As the accident has also greatly exposed the vulnerability of Japan’s energy security, it is crucial to clarify the path that Japan should take to maintain and secure its energy security in case of any possible future outbreak that may threaten its energy security. For this purpose, we conducted a comprehensive and structural analysis of Japan’s energy security based on APERC’s 4As framework and by using fuzzy logic and the Fuzzy-DEMATEL method to quantitatively understand the performance of Japan’s energy security and how the Fukushima accident had impacted the performance. Our results demonstrate that Japan’s energy security has clearly degraded after experiencing Fukushima accident. In addition, the results of the structural analysis by the Fuzzy-DEMATEL method show that the most salient dimension in the 4As framework for improving Japan’s energy security is the “Availability” dimension, and for this purpose nuclear energy and renewables play very important roles in securing the future energy security in Japan; this is consistent with the current energy policy measures announced in the Strategic Energy Plan of 2014.","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":"87953876","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}
A study is performed on a molten salt fast reactor （ MSFR ） of 1.5 GWe output. The reactor is started up by using transuranium elements reprocessed from spent fuel of a BWR. The fuel salt of the reactor is the mixed fluoride salt NaF – KF – UF 4 – TRUF 3 , which is reprocessed almost continuously by an oxide-precipitation process during the reactor operation. By performing calculations using the nuclear analysis code PIJ – BURN in SRAC2006 and the nuclear data file of JENDL – 3.3, the following re-sults are obtained. （ 1 ） The burn-up characteristics of the reactor are mainly determined by the uranium inventory （ U inv ） in the reactor and the reprocessing cycle （ L rep ） , which is the time interval necessary to reprocess all the fuel salt in the primary loop. （ 2 ） A large U inv and short L rep enhance the breeding performance of the reactor. （ 3 ） The period necessary to keep the radioactive waste under control will be about 400 years in the case of L rep longer than 400 efpd. （ 4 ） Power stations consisting of 20 MSFRs （ total output of 30 GWe ） can operate for 600 years by utilizing 14,000 t of uranium obtained from the spent fuel of LWRs in Japan.
{"title":"Performances of Molten-Salt Fast Reactor with Self-Sustainability","authors":"K. Mitachi","doi":"10.3327/TAESJ.J16.029","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.029","url":null,"abstract":"A study is performed on a molten salt fast reactor （ MSFR ） of 1.5 GWe output. The reactor is started up by using transuranium elements reprocessed from spent fuel of a BWR. The fuel salt of the reactor is the mixed fluoride salt NaF – KF – UF 4 – TRUF 3 , which is reprocessed almost continuously by an oxide-precipitation process during the reactor operation. By performing calculations using the nuclear analysis code PIJ – BURN in SRAC2006 and the nuclear data file of JENDL – 3.3, the following re-sults are obtained. （ 1 ） The burn-up characteristics of the reactor are mainly determined by the uranium inventory （ U inv ） in the reactor and the reprocessing cycle （ L rep ） , which is the time interval necessary to reprocess all the fuel salt in the primary loop. （ 2 ） A large U inv and short L rep enhance the breeding performance of the reactor. （ 3 ） The period necessary to keep the radioactive waste under control will be about 400 years in the case of L rep longer than 400 efpd. （ 4 ） Power stations consisting of 20 MSFRs （ total output of 30 GWe ） can operate for 600 years by utilizing 14,000 t of uranium obtained from the spent fuel of LWRs in Japan.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85249511","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":"Preparation of Sodium Uranates","authors":"Masayoshi Uno, K. Yokoyama, Y. Murakami","doi":"10.3327/TAESJ.J16.035","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.035","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75881984","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":"Evaluation of Ambient Dose Equivalent Rates Owing to Natural Radioactive Nuclides in Eastern Japan by Car-Borne Surveys Using KURAMA–II","authors":"M. Andoh, N. Matsuda, Kimiaki Saito","doi":"10.3327/TAESJ.J16.023","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.023","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87613758","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}
Since the Fukushima-Daiichi nuclear power station accident, the Japanese regulatory body has improved and upgraded the regulation of nuclear power plants, and continuous effort is required to enhance risk management in the midto long term. Earthquakes and tsunamis are considered as the most important risks, and the establishment of probabilistic risk assessment (PRA) methodologies for these events is a major issue of current PRA. The Nuclear Regulation Authority (NRA) addressed the PRA methodology for tsunamis induced by earthquakes, which is one of the methodologies that should be enhanced step by step for the improvement and maturity of PRA techniques. The AESJ standard for the procedure of seismic PRA for nuclear power plants in 2015 provides the basic concept of the methodology; however, details of the application to the actual plant PRA model have not been sufficiently provided. This study proposes a detailed PRA methodology for tsunamis induced by earthquakes using the DQFM methodology, which contributes to improving the safety of nuclear power plants. Furthermore, this study also states the issues which need more research.
{"title":"Proposal of Methodology of Tsunami Accident Sequence Analysis Induced by Earthquake Using DQFM Methodology","authors":"H. Muta, K. Muramatsu","doi":"10.3327/TAESJ.J16.019","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.019","url":null,"abstract":"Since the Fukushima-Daiichi nuclear power station accident, the Japanese regulatory body has improved and upgraded the regulation of nuclear power plants, and continuous effort is required to enhance risk management in the midto long term. Earthquakes and tsunamis are considered as the most important risks, and the establishment of probabilistic risk assessment (PRA) methodologies for these events is a major issue of current PRA. The Nuclear Regulation Authority (NRA) addressed the PRA methodology for tsunamis induced by earthquakes, which is one of the methodologies that should be enhanced step by step for the improvement and maturity of PRA techniques. The AESJ standard for the procedure of seismic PRA for nuclear power plants in 2015 provides the basic concept of the methodology; however, details of the application to the actual plant PRA model have not been sufficiently provided. This study proposes a detailed PRA methodology for tsunamis induced by earthquakes using the DQFM methodology, which contributes to improving the safety of nuclear power plants. Furthermore, this study also states the issues which need more research.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87186474","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}
Evaluation of the atmospheric-pressure change （ APC ） in a tornado is necessary to assess the integrity of nuclear-related facilities. The Rankine model has been most frequently used to theoretically calculate the APC in a tornado. The result, however, is considered to be overly conservative because the Rankine model wind speed at the ground is larger than that in reality. On the other hand, the wind speed of the Fujita model is closer to that of actual tornadoes but is expressed by more complicated algebraic equations than that in the Rankine model. Also, because it is impossible to analytical-ly derive the APC equation using the Fujita model, numerical computation is required. A previous study employed the finite element method （ FEM ） for such a purpose. However, a general-purpose FEM code often requires complicated input parameters. In order to conduct parametric studies to evaluate the integrity of facilities in various cases of tornadoes, the finite-difference method code “TORPEC”, which is specialized to analyze the APC, was developed as a convenient design tool. TORPEC is based on Poisson’s equation derived from the Navier-Stokes equation. It also runs on widely available technical calculation software such as Microsoft ® Excel VBA or MATLAB ® . Taking advantage of such convenience, various calculations have been conducted to reveal the characteristics of APC as functions of the maximum tangential wind speed, axial position and tornado radius. TORPEC is used as a benchmark in the existing paper. The case study results obtained by TORPEC show a constant ratio of the pressure drop of the Fujita model against the Rankine model. This factor can be used to derive the Fujita model result from the Rankine model result without FEM analysis.
{"title":"Evaluation of Atmospheric-Pressure Change in Tornado Using Fujita Model","authors":"Juntaro Shimizu, Shunsuke Ohtsubo","doi":"10.3327/TAESJ.J16.009","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.009","url":null,"abstract":"Evaluation of the atmospheric-pressure change （ APC ） in a tornado is necessary to assess the integrity of nuclear-related facilities. The Rankine model has been most frequently used to theoretically calculate the APC in a tornado. The result, however, is considered to be overly conservative because the Rankine model wind speed at the ground is larger than that in reality. On the other hand, the wind speed of the Fujita model is closer to that of actual tornadoes but is expressed by more complicated algebraic equations than that in the Rankine model. Also, because it is impossible to analytical-ly derive the APC equation using the Fujita model, numerical computation is required. A previous study employed the finite element method （ FEM ） for such a purpose. However, a general-purpose FEM code often requires complicated input parameters. In order to conduct parametric studies to evaluate the integrity of facilities in various cases of tornadoes, the finite-difference method code “TORPEC”, which is specialized to analyze the APC, was developed as a convenient design tool. TORPEC is based on Poisson’s equation derived from the Navier-Stokes equation. It also runs on widely available technical calculation software such as Microsoft ® Excel VBA or MATLAB ® . Taking advantage of such convenience, various calculations have been conducted to reveal the characteristics of APC as functions of the maximum tangential wind speed, axial position and tornado radius. TORPEC is used as a benchmark in the existing paper. The case study results obtained by TORPEC show a constant ratio of the pressure drop of the Fujita model against the Rankine model. This factor can be used to derive the Fujita model result from the Rankine model result without FEM analysis.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79185425","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}
Yuka WATANABE, Kazuhiko KUDO and Kazuya IDEMITSU Research Institute for East Asia Environments, Kyushu University Professor Emeritus at Kyushu University Department of Applied Quantum Physics and Nuclear Engineering, Graduate School of Engineering, Kyushu University, 744 Motooka, Nishi-ku, Fukuoka 819–0395, Japan (Received June 17, 2016; accepted in revised form September 28, 2016; published online January 11, 2017)
{"title":"Differences in opinions on nuclear power generation between Japanese and Korean university students","authors":"Yuka Watanabe, K. Kudo, K. Idemitsu","doi":"10.3327/TAESJ.J16.016","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.016","url":null,"abstract":"Yuka WATANABE, Kazuhiko KUDO and Kazuya IDEMITSU Research Institute for East Asia Environments, Kyushu University Professor Emeritus at Kyushu University Department of Applied Quantum Physics and Nuclear Engineering, Graduate School of Engineering, Kyushu University, 744 Motooka, Nishi-ku, Fukuoka 819–0395, Japan (Received June 17, 2016; accepted in revised form September 28, 2016; published online January 11, 2017)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91547635","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}
Akihiro YAMAMOTO and Naoto SEKIMURA Nuclear Safety Division, Safety and Environment Department, Fukui Prefectural Government, 3–17–1 Ote, Fukui-shi, Fukui 910–8580, Japan Department of Nuclear Engineering and Management, Graduate School of Engineering, The University of Tokyo, 7–3–1 Hongo, Bunkyo-ku, Tokyo 113–8656, Japan (Received April 11, 2016; accepted in revised form January 6, 2017; published online June 27, 2017)
{"title":"A Study on Enhancing the Effectiveness of Safety Culture in Nuclear Power Plants","authors":"A. Yamamoto, N. Sekimura","doi":"10.3327/TAESJ.J16.002","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.002","url":null,"abstract":"Akihiro YAMAMOTO and Naoto SEKIMURA Nuclear Safety Division, Safety and Environment Department, Fukui Prefectural Government, 3–17–1 Ote, Fukui-shi, Fukui 910–8580, Japan Department of Nuclear Engineering and Management, Graduate School of Engineering, The University of Tokyo, 7–3–1 Hongo, Bunkyo-ku, Tokyo 113–8656, Japan (Received April 11, 2016; accepted in revised form January 6, 2017; published online June 27, 2017)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91184433","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. Hamamoto, D. Tochio, T. Ishii, Hiroaki Sawahata
At the time of a reactor scram, the control rods are inserted into the high-temperature reactor core, where they are exposed to a thermal load. When a high-temperature engineering test reactor （ HTTR ） is constructed, the control rod temperature is evaluated conservatively because there is no way to accurately measure the actual temperature. In this study, to measure the temperature of the control rods in an HTTR, we installed a “melt wire” made of alloys with various melting points in the tips of the control rods. After experiencing a reactor scram at 100 ％ power, the melt wires were in-spected visually. The melt wires clearly showed a molten state. The result of the visual inspection claritied that the highest temperature reached at the tip of the control rods was in the range of 505 to 651 ℃ . The temperature measurement technique established by this study will lead to the improved accuracy of temperature estimation by design calculation and structural integrity assessment of the components in an HTTR.
{"title":"Temperature Measurement of Control Rod Using Melt Wire in High-Temperature Engineering Test Reactor (HTTR)","authors":"S. Hamamoto, D. Tochio, T. Ishii, Hiroaki Sawahata","doi":"10.3327/TAESJ.J16.036","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.036","url":null,"abstract":"At the time of a reactor scram, the control rods are inserted into the high-temperature reactor core, where they are exposed to a thermal load. When a high-temperature engineering test reactor （ HTTR ） is constructed, the control rod temperature is evaluated conservatively because there is no way to accurately measure the actual temperature. In this study, to measure the temperature of the control rods in an HTTR, we installed a “melt wire” made of alloys with various melting points in the tips of the control rods. After experiencing a reactor scram at 100 ％ power, the melt wires were in-spected visually. The melt wires clearly showed a molten state. The result of the visual inspection claritied that the highest temperature reached at the tip of the control rods was in the range of 505 to 651 ℃ . The temperature measurement technique established by this study will lead to the improved accuracy of temperature estimation by design calculation and structural integrity assessment of the components in an HTTR.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86605362","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 Structure for Fukushima Daiichi Nuclear Power Station Unit 3","authors":"I. Matsuo","doi":"10.3327/JAESJB.59.1_23","DOIUrl":"https://doi.org/10.3327/JAESJB.59.1_23","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84128035","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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