K. Kurosaki, Y. Kitano, Y. Ohishi, H. Muta, S. Yamanaka
The concept of utilizing a Zr - Er alloy in high-burnup fuel claddings in light water reactors has been proposed. Er in a Zr alloy is expected to act as a burnable poison that reduces the excess reactivi-ty. However, the required physical properties for practical realization of Zr - Er alloys have yet to be fully understood. Here, we prepared Zr - Er alloys with various Er contents and characterized the phase state, Young’s modulus, and thermal conductivity. The effect of Er content on the thermal and mechanical properties of the alloys was investigated.
{"title":"Phase State and Thermal and Mechanical Properties of Zr-Er Alloys","authors":"K. Kurosaki, Y. Kitano, Y. Ohishi, H. Muta, S. Yamanaka","doi":"10.3327/TAESJ.J14.040","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.040","url":null,"abstract":"The concept of utilizing a Zr - Er alloy in high-burnup fuel claddings in light water reactors has been proposed. Er in a Zr alloy is expected to act as a burnable poison that reduces the excess reactivi-ty. However, the required physical properties for practical realization of Zr - Er alloys have yet to be fully understood. Here, we prepared Zr - Er alloys with various Er contents and characterized the phase state, Young’s modulus, and thermal conductivity. The effect of Er content on the thermal and mechanical properties of the alloys was investigated.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"46 1","pages":"123-127"},"PeriodicalIF":0.0,"publicationDate":"2015-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80369790","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":"鉄道車両の保守とヒューマンファクター (特集 原子力・航空機・鉄道の保守におけるヒューマンファクター)","authors":"田仲 文郎","doi":"10.3327/jaesjb.57.2_78","DOIUrl":"https://doi.org/10.3327/jaesjb.57.2_78","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"45 1","pages":"87-90"},"PeriodicalIF":0.0,"publicationDate":"2015-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90264424","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":"福島県モニタリングポストのNaI(Tl)検出器波高分布データを用いた空気中I-131放射能濃度時間変化の推定","authors":"英夫 平山, 宏樹 松村, 芳仁 波戸, 俊哉 佐波","doi":"10.3327/TAESJ.J14.027","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.027","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"74 1 1","pages":"1-11"},"PeriodicalIF":0.0,"publicationDate":"2015-01-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87785249","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}
Y. Amano, Koji Watanabe, S. Tashiro, Y. Yamane, J. Ishikawa, Kazuo Yoshida, G. Uchiyama, H. Abe
Radioactive materials might be released into air as a result of the accidental boiling of highly active liquid waste (HALW) in reprocessing plants. In such accidents, volatile radioactive nuclides, such as ruthenium, are released from the tanks into the atmosphere. In addition to the radioactive materials, nitrogen oxides are also released owing to the thermal decomposition of metal nitrates in HALW. The released nitrogen oxides transport volatile ruthenium and cause redox reactions associated with the composition or decomposition of volatile ruthenium. In this study, data of nitrogen oxide release were obtained by heating simulated HALW to 600°C. Data were also obtained for mixed lanthanide solution, mixed lanthanide solution containing zirconium dioxide, and mixed lanthanide solution containing ruthenium dioxide. As a result, the release of nitrogen oxides from the simulated HALW was observed from 200°C to 600°C, and the main release of nitrogen oxides was observed at about 340°C. All the lanthanide nitrates were found to decompose in the simulated HALW, and the thermal decomposition temperature of the lanthanide nitrates decreased after the addition of ruthenium dioxide to the mixed lanthanide nitrate solution.
{"title":"Trends of Nitrogen Oxide Release during Thermal Decomposition of Nitrates in Highly Active Liquid Waste","authors":"Y. Amano, Koji Watanabe, S. Tashiro, Y. Yamane, J. Ishikawa, Kazuo Yoshida, G. Uchiyama, H. Abe","doi":"10.3327/TAESJ.J14.001","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.001","url":null,"abstract":"Radioactive materials might be released into air as a result of the accidental boiling of highly active liquid waste (HALW) in reprocessing plants. In such accidents, volatile radioactive nuclides, such as ruthenium, are released from the tanks into the atmosphere. In addition to the radioactive materials, nitrogen oxides are also released owing to the thermal decomposition of metal nitrates in HALW. The released nitrogen oxides transport volatile ruthenium and cause redox reactions associated with the composition or decomposition of volatile ruthenium. In this study, data of nitrogen oxide release were obtained by heating simulated HALW to 600°C. Data were also obtained for mixed lanthanide solution, mixed lanthanide solution containing zirconium dioxide, and mixed lanthanide solution containing ruthenium dioxide. As a result, the release of nitrogen oxides from the simulated HALW was observed from 200°C to 600°C, and the main release of nitrogen oxides was observed at about 340°C. All the lanthanide nitrates were found to decompose in the simulated HALW, and the thermal decomposition temperature of the lanthanide nitrates decreased after the addition of ruthenium dioxide to the mixed lanthanide nitrate solution.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"14 1","pages":"86-94"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81898569","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}
Fumio Hirano, Otani Yoshiteru, H. Kyokawa, M. Mihara, H. Shimizu, A. Honda
Fumio HIRANO, Yoshiteru OTANI, Hiroyuki KYOKAWA, Morihiro MIHARA, Hiroyuki SHIMIZU and Akira HONDA Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1112, Japan Civil Engineering Design Division, Kajima Corporation, 6-5-30 Akasaka, Minato-ku, Tokyo 107-8502, Japan Institute of Fluid Science, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577, Japan (Received September 10, 2015; accepted in revised form December 7, 2015; published online April 28, 2016)
{"title":"Crack Formation in Cementitious Materials Used for an Engineering Barrier System and Their Impact on Hydraulic Conductivity from the Viewpoint of Performance Assessment of a TRU Waste Disposal System","authors":"Fumio Hirano, Otani Yoshiteru, H. Kyokawa, M. Mihara, H. Shimizu, A. Honda","doi":"10.3327/TAESJ.J15.015","DOIUrl":"https://doi.org/10.3327/TAESJ.J15.015","url":null,"abstract":"Fumio HIRANO, Yoshiteru OTANI, Hiroyuki KYOKAWA, Morihiro MIHARA, Hiroyuki SHIMIZU and Akira HONDA Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1112, Japan Civil Engineering Design Division, Kajima Corporation, 6-5-30 Akasaka, Minato-ku, Tokyo 107-8502, Japan Institute of Fluid Science, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577, Japan (Received September 10, 2015; accepted in revised form December 7, 2015; published online April 28, 2016)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"14 1","pages":"97-114"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84178564","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 : 2015-01-01DOI: 10.1007/978-4-431-55543-8
M. Ishikawa
{"title":"A Study of the Fukushima Daiichi Nuclear Accident Process","authors":"M. Ishikawa","doi":"10.1007/978-4-431-55543-8","DOIUrl":"https://doi.org/10.1007/978-4-431-55543-8","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"86 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77146258","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}
An accident of evaporation to dryness by boiling of high-level liquid waste (HLLW) is postulated to be one of the severe accidents that may occur as a result of the loss of cooling function at a fuel reprocessing plant. In this case, some amount of nonvolatile fission products (FPs) will be transferred in the form of mist to the vapor phase in the tank, and could be released to the environment. Therefore, the quantitative estimation of the transfer rate is one of the key issues in the assessment of the accident consequences. To resolve this issue, a mechanistic correlation of the entrainment rate with upward vapor flow has been developed based on the data obtained from the experiments using simulated and actual HLLW.
{"title":"Development of Mechanistic Entrainment Correlation in Accident of Evaporation to Dryness by Boiling of Reprocessed High-Level Liquid Waste","authors":"Kazuo Yoshida","doi":"10.3327/TAESJ.J14.022","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.022","url":null,"abstract":"An accident of evaporation to dryness by boiling of high-level liquid waste (HLLW) is postulated to be one of the severe accidents that may occur as a result of the loss of cooling function at a fuel reprocessing plant. In this case, some amount of nonvolatile fission products (FPs) will be transferred in the form of mist to the vapor phase in the tank, and could be released to the environment. Therefore, the quantitative estimation of the transfer rate is one of the key issues in the assessment of the accident consequences. To resolve this issue, a mechanistic correlation of the entrainment rate with upward vapor flow has been developed based on the data obtained from the experiments using simulated and actual HLLW.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"123 1","pages":"40-50"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77607801","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. Hirayama, K. Kondo, Y. Unno, H. Matsumura, H. Iwase, A. Yunoki, S. Sasaki
Hideo HIRAYAMA, Kenjiro KONDO, Yasuhiro UNNO, Hiroshi MATSUMURA, Hiroshi IWASE, Akira YUNOKI and Shinichi SASAKI High Energy Accelerator Research Organization, 1-1 Oho, Tsukubashi, Ibaraki 305-0801, Japan National Institute of Advanced Industrial Science and Technology, 1-1-1 Umezono, Tsukubashi, Ibaraki 305-8568, Japan (Received February 28, 2015; accepted in revised form April 20, 2015; published online June 30, 2015)
{"title":"Rapid and simple measurement method of 90 Sr concentration in water by measuring β-rays from 90 Y","authors":"H. Hirayama, K. Kondo, Y. Unno, H. Matsumura, H. Iwase, A. Yunoki, S. Sasaki","doi":"10.3327/TAESJ.J14.048","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.048","url":null,"abstract":"Hideo HIRAYAMA, Kenjiro KONDO, Yasuhiro UNNO, Hiroshi MATSUMURA, Hiroshi IWASE, Akira YUNOKI and Shinichi SASAKI High Energy Accelerator Research Organization, 1-1 Oho, Tsukubashi, Ibaraki 305-0801, Japan National Institute of Advanced Industrial Science and Technology, 1-1-1 Umezono, Tsukubashi, Ibaraki 305-8568, Japan (Received February 28, 2015; accepted in revised form April 20, 2015; published online June 30, 2015)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"58 1","pages":"141-150"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91428789","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}
An accident of evaporation to dryness caused by boiling of high-level liquid waste (HLLW) is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, some amount of fission products (FPs) will be transferred to the vapor phase in the tank, and could be released to the environment. Therefore, the quantitative estimation of the transport and release behavior of FPs is one of the key issues in the assessment of the accident consequence. To resolve this issue, a systematic analysis method with computer codes has been developed on the basis of the phenomenological behavior in the accident of evaporation to dryness caused by boiling of HLLW. A simulation study demonstrated that the behavior of liquid waste temperature and the entrainment of mists were in good agreement with the experimental results during the early boiling stage, and that some issues to be resolved were pointed out for the estimation of the amount of transferred Ru to the vapor phase at the late boiling stage.
{"title":"Analysis of Release and Transport of Aerial Radioactive Materials in Accident of Evaporation to Dryness Caused by Boiling of Reprocessed High-Level Liquid Waste","authors":"Kazuo Yoshida, J. Ishikawa, H. Abe","doi":"10.3327/TAESJ.J15.002","DOIUrl":"https://doi.org/10.3327/TAESJ.J15.002","url":null,"abstract":"An accident of evaporation to dryness caused by boiling of high-level liquid waste (HLLW) is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, some amount of fission products (FPs) will be transferred to the vapor phase in the tank, and could be released to the environment. Therefore, the quantitative estimation of the transport and release behavior of FPs is one of the key issues in the assessment of the accident consequence. To resolve this issue, a systematic analysis method with computer codes has been developed on the basis of the phenomenological behavior in the accident of evaporation to dryness caused by boiling of HLLW. A simulation study demonstrated that the behavior of liquid waste temperature and the entrainment of mists were in good agreement with the experimental results during the early boiling stage, and that some issues to be resolved were pointed out for the estimation of the amount of transferred Ru to the vapor phase at the late boiling stage.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"33 1","pages":"213-226"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86944647","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. Tashiro, Y. Amano, Kazuo Yoshida, Y. Yamane, G. Uchiyama, H. Abe
The release characteristics of Ru from highly active liquid waste （ HALW ） have been investigated under the condition of accidental evaporation to dryness by boiling of HALW. Using a laboratory-scale apparatus, the simulated HALW （ s - HALW ） was heated with an external heater to dryness to observe the release characteristics of Ru and gaseous nitrogen oxides. As a result, Ru was significantly released between 120 and 300 ℃ of the s - HALW. The cumulative release ratio of Ru was 0.088. It was also found that the partially released amount of Ru against the temperature of the s - HALW had two peaks at about 140 ℃ and about 240 ℃ . Referring to the results of the release rate of gaseous nitrogen oxides and the volume of condensate, which was a collection of the mixed vapors of steam and nitric acid released from the s - HALW, we discussed the causes of Ru release around these peaks.
{"title":"Release Characteristics of Ruthenium from Highly Active Liquid Waste in Drying Step","authors":"S. Tashiro, Y. Amano, Kazuo Yoshida, Y. Yamane, G. Uchiyama, H. Abe","doi":"10.3327/TAESJ.J14.028","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.028","url":null,"abstract":"The release characteristics of Ru from highly active liquid waste （ HALW ） have been investigated under the condition of accidental evaporation to dryness by boiling of HALW. Using a laboratory-scale apparatus, the simulated HALW （ s - HALW ） was heated with an external heater to dryness to observe the release characteristics of Ru and gaseous nitrogen oxides. As a result, Ru was significantly released between 120 and 300 ℃ of the s - HALW. The cumulative release ratio of Ru was 0.088. It was also found that the partially released amount of Ru against the temperature of the s - HALW had two peaks at about 140 ℃ and about 240 ℃ . Referring to the results of the release rate of gaseous nitrogen oxides and the volume of condensate, which was a collection of the mixed vapors of steam and nitric acid released from the s - HALW, we discussed the causes of Ru release around these peaks.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"39 1","pages":"227-234"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81152455","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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