Y. Okamoto, T. Nagai, H. Shiwaku, Takehiko Inose, Sato Seiichi
X-ray absorption fine structure （ XAFS ） and imaging XAFS analyses were performed to elucidate the chemical state of rhodium in simulated waste glass. The chemical forms of Rh in the glass were evaluated to be 84 ％ RhO 2 and 16 ％ metal / alloy as the result of linear combination analysis of EXAFS data. According to the imaging XAFS analysis, the chemical form of Rh that was located together with Ru was mainly oxide （ RhO 2 ） . This suggests that a stable （ Ru,Rh ） O 2 solid solution exists in the simulated glass. On the other hand, that of Rh whose distribution did not coincide with Ru in the glass was mainly metallic. The metallic Rh in the glass tended to become an aggregate form. It can be concluded that the chemical state of Rh was strongly affected by the existence and distribution of Ru.
{"title":"Chemical State Analysis of Rhodium in Simulated Waste Glass by Synchrotron-Radiation-based XAFS and Imaging XAFS Techniques","authors":"Y. Okamoto, T. Nagai, H. Shiwaku, Takehiko Inose, Sato Seiichi","doi":"10.3327/TAESJ.J16.024","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.024","url":null,"abstract":"X-ray absorption fine structure （ XAFS ） and imaging XAFS analyses were performed to elucidate the chemical state of rhodium in simulated waste glass. The chemical forms of Rh in the glass were evaluated to be 84 ％ RhO 2 and 16 ％ metal / alloy as the result of linear combination analysis of EXAFS data. According to the imaging XAFS analysis, the chemical form of Rh that was located together with Ru was mainly oxide （ RhO 2 ） . This suggests that a stable （ Ru,Rh ） O 2 solid solution exists in the simulated glass. On the other hand, that of Rh whose distribution did not coincide with Ru in the glass was mainly metallic. The metallic Rh in the glass tended to become an aggregate form. It can be concluded that the chemical state of Rh was strongly affected by the existence and distribution of Ru.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"87 1","pages":"180-190"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85339132","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 Xe-135, I-131, I-132, I-133 and Te-132 concentrations in plumes at the monitoring posts in Fukushima prefecture in March 2011 were estimated using the pulse height distribution obtained from a NaI (Tl) detector, which were available to the public. Several corrections to the pulse height distribution were necessary owing to high count rates. The contribution to the count rates from each radionuclide except Xe-135 accumulated around each monitoring post was estimated using a method based on the time history of the peak count rate proposed by the authors. The concentration of each radionuclide in the plume was converted from the peak count rate using the response of the NaI (Tl) detector calculated with the egs5 code for a model of a plume containing a uniform distribution of radionuclides. The obtained time histories of Xe-135, I-131, I-132, I-133 and Te-132 concentrations in air at a fixed point in March 2011 were the first ones for Fukushima prefecture. The results at five monitoring posts near Fukushima Daiichi Nuclear Power Station were used to characterize radionuclides in the plume before March 15, soon after the accident. The results at three monitoring posts, Naraha-town Shoukan, Hirono-town Futatsunuma and Fukushima-city Momijiyama, which were analyzed during almost all of March, were used to characterize radionuclides in the plume in the period after March 14. It was fourd that Xe-135 was dominant on March 12 and Te-132 increased from March 13. For the radionuclides of iodine, I-131, I-132 and I-133 were detected with almost the same concentration for the first few days after the reactor shutdown.
{"title":"Estimation of Xe-135, I-131, I-132, I-133 and Te-132 Concentrations in Plumes at Monitoring Posts in Fukushima Prefecture Using Pulse Height Distribution Obtained from NaI(Tl) Detector","authors":"H. Hirayama, H. Matsumura, Y. Namito, T. Sanami","doi":"10.3327/taesj.j16.014","DOIUrl":"https://doi.org/10.3327/taesj.j16.014","url":null,"abstract":"The Xe-135, I-131, I-132, I-133 and Te-132 concentrations in plumes at the monitoring posts in Fukushima prefecture in March 2011 were estimated using the pulse height distribution obtained from a NaI (Tl) detector, which were available to the public. Several corrections to the pulse height distribution were necessary owing to high count rates. The contribution to the count rates from each radionuclide except Xe-135 accumulated around each monitoring post was estimated using a method based on the time history of the peak count rate proposed by the authors. The concentration of each radionuclide in the plume was converted from the peak count rate using the response of the NaI (Tl) detector calculated with the egs5 code for a model of a plume containing a uniform distribution of radionuclides. The obtained time histories of Xe-135, I-131, I-132, I-133 and Te-132 concentrations in air at a fixed point in March 2011 were the first ones for Fukushima prefecture. The results at five monitoring posts near Fukushima Daiichi Nuclear Power Station were used to characterize radionuclides in the plume before March 15, soon after the accident. The results at three monitoring posts, Naraha-town Shoukan, Hirono-town Futatsunuma and Fukushima-city Momijiyama, which were analyzed during almost all of March, were used to characterize radionuclides in the plume in the period after March 14. It was fourd that Xe-135 was dominant on March 12 and Te-132 increased from March 13. For the radionuclides of iodine, I-131, I-132 and I-133 were detected with almost the same concentration for the first few days after the reactor shutdown.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"54 1","pages":"1-14"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81314300","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}
Shizuka Takai, S. Takeda, Ryutaro Sakai, T. Shimada, M. Munakata, T. Tanaka
In geological disposal, the direct effect of active faults on geological repositories is avoided at the stage of site characterization; however, uncertainty remains for the avoidance of faults derived from active faults, which are concealed deep under the ground and are dif fi cult to detect by site investigation. In this research, the in fl uence of the growth of undetected splay faults on a natural barrier in a geological disposal system due to the future action of faults was evaluated. We investigated examples of splay faults in Japan and set conditions for the growth of splay faults. Furthermore, we assumed a disposal site composed of sedimentary rock and made a hydrogeological model of the growth of splay faults. We carried out groundwater fl ow analyses, changing parameters such as the location and depth of the repository and the growth velocity of splay faults. The results indicate that the main fl ow path from the repository is changed into an upward fl ow along the splay fault due to its growth and that the average velocity to the ground surface becomes one or two orders of magnitude higher than that before its growth. The results also suggest that splay fault growth leads to the possibility of the downward fl ow of oxidizing groundwater from the ground surface area.
{"title":"Evaluation of Influence of Splay Fault Growth on Groundwater Flow around Geological Disposal System","authors":"Shizuka Takai, S. Takeda, Ryutaro Sakai, T. Shimada, M. Munakata, T. Tanaka","doi":"10.3327/TAESJ.J16.003","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.003","url":null,"abstract":"In geological disposal, the direct effect of active faults on geological repositories is avoided at the stage of site characterization; however, uncertainty remains for the avoidance of faults derived from active faults, which are concealed deep under the ground and are dif fi cult to detect by site investigation. In this research, the in fl uence of the growth of undetected splay faults on a natural barrier in a geological disposal system due to the future action of faults was evaluated. We investigated examples of splay faults in Japan and set conditions for the growth of splay faults. Furthermore, we assumed a disposal site composed of sedimentary rock and made a hydrogeological model of the growth of splay faults. We carried out groundwater fl ow analyses, changing parameters such as the location and depth of the repository and the growth velocity of splay faults. The results indicate that the main fl ow path from the repository is changed into an upward fl ow along the splay fault due to its growth and that the average velocity to the ground surface becomes one or two orders of magnitude higher than that before its growth. The results also suggest that splay fault growth leads to the possibility of the downward fl ow of oxidizing groundwater from the ground surface area.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"44 1","pages":"34-48"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74218159","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}
Zirconium （ Zr ） has been used as a structural material at the spent nuclear fuel reprocessing plant in Japan because of its excellent corrosion resistance against nitric acid solution. However, radiolytic hydrogen is known to be generated in spent nuclear fuel solution. Zr is known to be highly susceptible to hydrogen embrittlement. Therefore, evaluating the radiolytic hydrogen absorption behavior of Zr in nitric acid solution （ HNO 3 ） is essential. In this study, immersion tests were conducted on Zr in nitric acid solutions under γ -ray irradiation to evaluate its radiolytic hydrogen absorption behavior. Results showed that the hydrogen concentration on Zr increased in both 1 – 3 mol / L HNO 3 and pure water upon irradiation of 5 and 7 kGy / h after immersion. The amount of hydrogen absorption on Zr under γ -ray irradiation had a direct correlation with the amount of radiolytic hydrogen generated in HNO 3 . The results of glow discharge optical emission spectrometry, thermal desorption spectrosco-py, and X-ray diffraction show that the absorbed radiolytic hydrogen generated a hydride on the surface of Zr.
由于锆(Zr)具有优异的耐硝酸腐蚀性能，在日本乏燃料后处理装置中被用作结构材料。然而，已知在乏核燃料溶液中会产生放射性裂变氢。众所周知，Zr对氢脆非常敏感。因此，评价Zr在硝酸溶液(hno3)中的辐射溶氢行为是必要的。在本研究中，对Zr在硝酸溶液中进行了γ射线辐照浸泡试验，以评价其辐射溶氢行为。结果表明:浸泡5、7 kGy / h后，在1 ~ 3 mol / L hno3和纯水中，Zr上的氢浓度均增加;Zr在γ射线照射下的吸氢量与hno3中产生的辐射解氢量有直接关系。辉光发射光谱、热解吸光谱和x射线衍射结果表明，吸收的辐射解氢在Zr表面生成氢化物。
{"title":"Hydrogen Absorption Behavior on Zirconium under γ-Radiolysis of Nitric Acid Solution","authors":"Y. Ishijima, F. Ueno, H. Abe","doi":"10.3327/TAESJ.J16.018","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.018","url":null,"abstract":"Zirconium （ Zr ） has been used as a structural material at the spent nuclear fuel reprocessing plant in Japan because of its excellent corrosion resistance against nitric acid solution. However, radiolytic hydrogen is known to be generated in spent nuclear fuel solution. Zr is known to be highly susceptible to hydrogen embrittlement. Therefore, evaluating the radiolytic hydrogen absorption behavior of Zr in nitric acid solution （ HNO 3 ） is essential. In this study, immersion tests were conducted on Zr in nitric acid solutions under γ -ray irradiation to evaluate its radiolytic hydrogen absorption behavior. Results showed that the hydrogen concentration on Zr increased in both 1 – 3 mol / L HNO 3 and pure water upon irradiation of 5 and 7 kGy / h after immersion. The amount of hydrogen absorption on Zr under γ -ray irradiation had a direct correlation with the amount of radiolytic hydrogen generated in HNO 3 . The results of glow discharge optical emission spectrometry, thermal desorption spectrosco-py, and X-ray diffraction show that the absorbed radiolytic hydrogen generated a hydride on the surface of Zr.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"41 1","pages":"100-106"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77813751","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}
K. Wakasugi, M. Yamaguchi, S. Koo, Fumiya Nagao, Tomoko Kato, Yuji Suzuki, T. Ebashi, H. Umeki, Y. Niibori
{"title":"隆起・侵食による地質・地表環境の長期的変動を考慮した地層処分の安全評価手法の開発","authors":"K. Wakasugi, M. Yamaguchi, S. Koo, Fumiya Nagao, Tomoko Kato, Yuji Suzuki, T. Ebashi, H. Umeki, Y. Niibori","doi":"10.3327/TAESJ.J16.010","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.010","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"1 1","pages":"15-33"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79163659","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. Muta, K. Muramatsu, Y. Kameko, H. Miura, K. Ogura, Tsuyoshi Uchida
the severe accident the Fukushima-Daiichi nuclear power station, the regulation of nuclear plant safety in Japan was upgraded, and continuous effort to enhance risk management in the medium and long term is required. Seismic risk is important in Japan, and one of the major issues of current probabilistic risk assessment （ PRA ） methodology is the enhancement of seismic PRA including the evaluation of initiating events induced by simultaneous multiple failures of components and of subsequent accident sequences. The Nuclear Regulation Authority （ NRA ） addressed the issue as “…multiple-failure-initiating events should be considered.” In addition, the standard for the procedure of seismic PRA for nuclear power plants in 2015 identifies this issue in the same manner. This study proposes an enhanced seismic PRA methodology considering multiple-failure-initiating events that is expected to contribute to improving the safety of nuclear power plants. This study also discusses the issues that need more research for their resolution.
{"title":"Proposal of Evaluation Methodology of Multiple-Failure-Initiating Events for Seismic PRA","authors":"H. Muta, K. Muramatsu, Y. Kameko, H. Miura, K. Ogura, Tsuyoshi Uchida","doi":"10.3327/TAESJ.J16.013","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.013","url":null,"abstract":"the severe accident the Fukushima-Daiichi nuclear power station, the regulation of nuclear plant safety in Japan was upgraded, and continuous effort to enhance risk management in the medium and long term is required. Seismic risk is important in Japan, and one of the major issues of current probabilistic risk assessment （ PRA ） methodology is the enhancement of seismic PRA including the evaluation of initiating events induced by simultaneous multiple failures of components and of subsequent accident sequences. The Nuclear Regulation Authority （ NRA ） addressed the issue as “…multiple-failure-initiating events should be considered.” In addition, the standard for the procedure of seismic PRA for nuclear power plants in 2015 identifies this issue in the same manner. This study proposes an enhanced seismic PRA methodology considering multiple-failure-initiating events that is expected to contribute to improving the safety of nuclear power plants. This study also discusses the issues that need more research for their resolution.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"42 1","pages":"89-99"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87289960","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}
Akitoshi Hotta, Akinobu Morita, M. Kajimoto, Y. Maruyama
Among twelve FCI cases examined in the OECD / NEA / CSNI / SERENA2 test series using two facilities, six steam explosion cases, five from TROI and one from KROTOS, were analyzed by JASMINE V.3. The major model parameters were categorized into the “focused zone”, i,e., the core part of interest, and the “peripheral zone”, corresponding to the initial and boundary conditions given intentionally for each test case. For the former, base values established through past validation studies of JASMINE V.3 were applied. The code was modified to implement the measured distribution of the entrained droplet size acquired in TROI – VISU. For the latter, melt release histories were given as a combination of time tables of jet diameter and release velocity that were estimated from image data and transit timing data of the melt leading edge. The base values were shown to predict impulse re-sponses of SERENA2 systematically with a reasonable error band. A statistical analysis based on the LHS method was performed. Uncertainty ranges were given on the basis of measurement errors and past validation studies in the development of JASMINE. Underlying mechanisms causing apparent differences in the mechanical energy conversion ratio between two facilities were studied from the viewpoint of breakup length and trigger timing.
{"title":"Simulation of Fuel-Coolant Interaction SERENA2 Test based on JASMINE Version 3","authors":"Akitoshi Hotta, Akinobu Morita, M. Kajimoto, Y. Maruyama","doi":"10.3327/taesj.j16.028","DOIUrl":"https://doi.org/10.3327/taesj.j16.028","url":null,"abstract":"Among twelve FCI cases examined in the OECD / NEA / CSNI / SERENA2 test series using two facilities, six steam explosion cases, five from TROI and one from KROTOS, were analyzed by JASMINE V.3. The major model parameters were categorized into the “focused zone”, i,e., the core part of interest, and the “peripheral zone”, corresponding to the initial and boundary conditions given intentionally for each test case. For the former, base values established through past validation studies of JASMINE V.3 were applied. The code was modified to implement the measured distribution of the entrained droplet size acquired in TROI – VISU. For the latter, melt release histories were given as a combination of time tables of jet diameter and release velocity that were estimated from image data and transit timing data of the melt leading edge. The base values were shown to predict impulse re-sponses of SERENA2 systematically with a reasonable error band. A statistical analysis based on the LHS method was performed. Uncertainty ranges were given on the basis of measurement errors and past validation studies in the development of JASMINE. Underlying mechanisms causing apparent differences in the mechanical energy conversion ratio between two facilities were studied from the viewpoint of breakup length and trigger timing.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"16 1","pages":"139-152"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86885892","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}
In TEPCO’s Fukushima Dai-ichi Nuclear Power Station accident on March 11, 2011, a massive number of radionuclides were released from Unit–1, Unit–2, and Unit–3 to the environment. After the accident, the effects of multiple sources became one of the major topics of discussion in safety assessment. However, these discussions mainly focused on core damage frequencies. In the case of simultaneous accidents at multiple units, it is important to consider not only core damage frequencies but also risks because radionuclides are released from multiple units to the environment. In this study, we analyzed dominant parameters that affect health in the case of multiple sources with a simplified configuration of units. The analytical results show that the probabilities of early health effects near the site boundary depend on the locations of units and the wind direction at the site. They also show that the probabilities of early health effects due to releases from multiple units cannot be calculated by the arithmetic summation of probabilities of early health effects due to releases from single units because, for example, of the nonlinearity due to the threshold of the occurrence probability of early health effects.
{"title":"Analysis of the Effects of Multiple Radionuclide Plumes under Severe Accident Conditions on Environment around a Site Boundary","authors":"Kyoko Funayama, M. Kajimoto","doi":"10.3327/taesj.j16.033","DOIUrl":"https://doi.org/10.3327/taesj.j16.033","url":null,"abstract":"In TEPCO’s Fukushima Dai-ichi Nuclear Power Station accident on March 11, 2011, a massive number of radionuclides were released from Unit–1, Unit–2, and Unit–3 to the environment. After the accident, the effects of multiple sources became one of the major topics of discussion in safety assessment. However, these discussions mainly focused on core damage frequencies. In the case of simultaneous accidents at multiple units, it is important to consider not only core damage frequencies but also risks because radionuclides are released from multiple units to the environment. In this study, we analyzed dominant parameters that affect health in the case of multiple sources with a simplified configuration of units. The analytical results show that the probabilities of early health effects near the site boundary depend on the locations of units and the wind direction at the site. They also show that the probabilities of early health effects due to releases from multiple units cannot be calculated by the arithmetic summation of probabilities of early health effects due to releases from single units because, for example, of the nonlinearity due to the threshold of the occurrence probability of early health effects.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"35 1","pages":"191-196"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89731152","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}
T. Ashida, Hideaki Ito, Kazuyuki Miyamoto, Toshiyuki Nakamura, K. Koga, Norikazu Oohara, Hiroichi Ino
Takashi ASHIDA, Hideaki ITO, Kazuyuki MIYAMOTO, Toshiyuki NAKAMURA, Kazuhiro KOGA, Norikazu OOHARA and Hiroichi INO Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393, Japan Fuji Electric Co., Ltd., 1-1 Tanabeshinden, Kawasaki-ku, Kawasaki 210-9530, Japan (Received March 22, 2016; accepted in revised form June 22, 2016; published online October 6, 2016)
{"title":"Development of inspection and repair techniques in reactor vessel of experimental fast reactor \"Joyo\": Retrieval of the bent test subassembly","authors":"T. Ashida, Hideaki Ito, Kazuyuki Miyamoto, Toshiyuki Nakamura, K. Koga, Norikazu Oohara, Hiroichi Ino","doi":"10.3327/TAESJ.J15.032","DOIUrl":"https://doi.org/10.3327/TAESJ.J15.032","url":null,"abstract":"Takashi ASHIDA, Hideaki ITO, Kazuyuki MIYAMOTO, Toshiyuki NAKAMURA, Kazuhiro KOGA, Norikazu OOHARA and Hiroichi INO Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393, Japan Fuji Electric Co., Ltd., 1-1 Tanabeshinden, Kawasaki-ku, Kawasaki 210-9530, Japan (Received March 22, 2016; accepted in revised form June 22, 2016; published online October 6, 2016)","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"20 1 1","pages":"210-222"},"PeriodicalIF":0.0,"publicationDate":"2016-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83621313","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 Security and Safety Fuel for Pu-burner HTGR","authors":"S. Ueta","doi":"10.1115/ICONE25-67530","DOIUrl":"https://doi.org/10.1115/ICONE25-67530","url":null,"abstract":"","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2016-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73072529","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}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：