It is necessary to consider the effect of photoneutrons produced by photonuclear reactions in the shielding calculation of a medical linac room with incident electron greater than 10 MeV. For copper and tungsten used as the target materials of linac, we compared the experimental data with the eval-uated data in four photonuclear reaction files of photoneutron production cross sections. We also com pared the calculated results using four photonuclear files with experimental results on the angular distributions of photoneutrons emitted from targets bombarded by 18 and 28 MeV electrons. Conse-quently, we found that the shielding calculations by LA150 and JENDL / PD - 2016.1 gave the dose rates within a factor of 1.5 of accuracy in the electron energy of less than 28 MeV.
{"title":"Comparison of Photonuclear Data Files Used in Shielding Calculation of a Medical Linac Room","authors":"K. Kosako, Takashi Nakamura","doi":"10.3327/TAESJ.J20.005","DOIUrl":"https://doi.org/10.3327/TAESJ.J20.005","url":null,"abstract":"It is necessary to consider the effect of photoneutrons produced by photonuclear reactions in the shielding calculation of a medical linac room with incident electron greater than 10 MeV. For copper and tungsten used as the target materials of linac, we compared the experimental data with the eval-uated data in four photonuclear reaction files of photoneutron production cross sections. We also com pared the calculated results using four photonuclear files with experimental results on the angular distributions of photoneutrons emitted from targets bombarded by 18 and 28 MeV electrons. Conse-quently, we found that the shielding calculations by LA150 and JENDL / PD - 2016.1 gave the dose rates within a factor of 1.5 of accuracy in the electron energy of less than 28 MeV.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437484","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. Sanada, H. Kurikami, H. Funaki, K. Yoshimura, Tomohisa Abe, Mutsushi Ishida, S. Tanimori, R. Sato
The Japanese government is beginning to consider radiation protection in the “ specific reconstruc tion reproduction base area” of the Fukushima nuclear power plant, the evacuation order of which will be lifted by 2023. It is essential to grasp the present situation of radiation contamination and evaluate exposure dose in the area to realize the lifting of this evacuation order zone. Many surveys on the evaluation of the distributions of air dose rate have been carried out, and exposure dose has been esti-mated using the results since the Fukushima Daiichi Nuclear Power Plant accident. Nevertheless, more detailed information on exposure is needed for the area because the radiation level is relatively high. This will also be helpful in preparing a prudent evaluation plan. This study is aimed at evaluat-ing the detailed contamination situation in the area and estimating exposure dose with consideration of areal circumstances. Work was carried out for （ 1 ） an airborne survey of the air dose rate using an unmanned helicopter and ground-based measurement （ walk-survey ） , （ 2 ） the evaluation of airborne radiocesium and （ 3 ） the estimation of external / internal effective doses for the typical life patterns as-sumed. Our study resulted in a detailed map of the air dose rate and clarified the distribution pattern in the area. Moreover, the exposure dose of residents was evaluated by considering some life patterns based on this map.
{"title":"Radiation monitoring and evaluation of exposure doses to lift the evacuation orders for the zones designated for reconstruction and recovery","authors":"Y. Sanada, H. Kurikami, H. Funaki, K. Yoshimura, Tomohisa Abe, Mutsushi Ishida, S. Tanimori, R. Sato","doi":"10.3327/TAESJ.J20.021","DOIUrl":"https://doi.org/10.3327/TAESJ.J20.021","url":null,"abstract":"The Japanese government is beginning to consider radiation protection in the “ specific reconstruc tion reproduction base area” of the Fukushima nuclear power plant, the evacuation order of which will be lifted by 2023. It is essential to grasp the present situation of radiation contamination and evaluate exposure dose in the area to realize the lifting of this evacuation order zone. Many surveys on the evaluation of the distributions of air dose rate have been carried out, and exposure dose has been esti-mated using the results since the Fukushima Daiichi Nuclear Power Plant accident. Nevertheless, more detailed information on exposure is needed for the area because the radiation level is relatively high. This will also be helpful in preparing a prudent evaluation plan. This study is aimed at evaluat-ing the detailed contamination situation in the area and estimating exposure dose with consideration of areal circumstances. Work was carried out for （ 1 ） an airborne survey of the air dose rate using an unmanned helicopter and ground-based measurement （ walk-survey ） , （ 2 ） the evaluation of airborne radiocesium and （ 3 ） the estimation of external / internal effective doses for the typical life patterns as-sumed. Our study resulted in a detailed map of the air dose rate and clarified the distribution pattern in the area. Moreover, the exposure dose of residents was evaluated by considering some life patterns based on this map.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"27 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437572","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}
Yoshitaka Ichihara, N. Nakamura, H. Moritani, Tomohiro Horiguchi, Byunghyun Choi
In this study, we aim to approximately evaluate the effect of nonlinearity of reinforced concrete structures through seismic response analysis using the equivalent linear analysis method. A simulation analysis was performed for the ultimate response test of the shear wall of the reactor building used in an international competition by OECD / NEA in 1996. The equivalent stiffness and damping of the shear wall were obtained from the trilinear skeleton curves proposed by the Japan Electric Association and the hysteresis curves proposed by Cheng et al. The dominant frequency, maximum acceleration response, maximum displacement response, inertia force-displacement relationship, and acceleration response spectra of the top slab could be simulated well up to a shear strain of approximately γ ＝ 2.0 × 10 － 3 . The equivalent linear analysis used herein underestimates the maximum displacement response at the time of ultimate fracture of approximately γ ＝ 4.0 × 10 － 3 . Moreover, the maximum shear strain of the shear wall could not capture the locally occurring shear strain compared with that of the nonlinear analysis. Therefore, when employing this method to evaluate the maximum shear strain and test results, including those during the sudden increase in displacement immediately before the fracture, sufficient attention must be paid to its applicability.
{"title":"Applicability of Equivalent Linear Analysis to Reinforced Concrete Shear Walls: 3D FEM Simulation of Experiment Results of Seismic Wall Ultimate Behavior","authors":"Yoshitaka Ichihara, N. Nakamura, H. Moritani, Tomohiro Horiguchi, Byunghyun Choi","doi":"10.3327/taesj.j20.038","DOIUrl":"https://doi.org/10.3327/taesj.j20.038","url":null,"abstract":"In this study, we aim to approximately evaluate the effect of nonlinearity of reinforced concrete structures through seismic response analysis using the equivalent linear analysis method. A simulation analysis was performed for the ultimate response test of the shear wall of the reactor building used in an international competition by OECD / NEA in 1996. The equivalent stiffness and damping of the shear wall were obtained from the trilinear skeleton curves proposed by the Japan Electric Association and the hysteresis curves proposed by Cheng et al. The dominant frequency, maximum acceleration response, maximum displacement response, inertia force-displacement relationship, and acceleration response spectra of the top slab could be simulated well up to a shear strain of approximately γ ＝ 2.0 × 10 － 3 . The equivalent linear analysis used herein underestimates the maximum displacement response at the time of ultimate fracture of approximately γ ＝ 4.0 × 10 － 3 . Moreover, the maximum shear strain of the shear wall could not capture the locally occurring shear strain compared with that of the nonlinear analysis. Therefore, when employing this method to evaluate the maximum shear strain and test results, including those during the sudden increase in displacement immediately before the fracture, sufficient attention must be paid to its applicability.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437708","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}
Naoyuki TAMURA, Taiji CHIDA, Seong-Yun KIM and Yuichi NIIBORI Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University,6–6–01–2 Aza-Aoba, Aramaki, Aoba-ku, Sendai 980–8579, Japan Disposal Business Division, Japan Nuclear Fuel Limited, 504–22 Nozuki, Obuchi, Rokkasyo-mura, Kamikita-gun, Aomori 039–3212, Japan (Received October 12, 2020; accepted in revised form March 10, 2021; published online July 30, 2021)
{"title":"Sorption Behavior of Cesium on Calcium Silicate Hydrate Gel Formed as Secondary Mineral under the Coexistence Condition of Sulfate Ions","authors":"N. Tamura, Taiji Chida, Seong Yun Kim, Y. Niibori","doi":"10.3327/taesj.j20.017","DOIUrl":"https://doi.org/10.3327/taesj.j20.017","url":null,"abstract":"Naoyuki TAMURA, Taiji CHIDA, Seong-Yun KIM and Yuichi NIIBORI Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University,6–6–01–2 Aza-Aoba, Aramaki, Aoba-ku, Sendai 980–8579, Japan Disposal Business Division, Japan Nuclear Fuel Limited, 504–22 Nozuki, Obuchi, Rokkasyo-mura, Kamikita-gun, Aomori 039–3212, Japan (Received October 12, 2020; accepted in revised form March 10, 2021; published online July 30, 2021)","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69438005","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":"Qualitative Data Analysis of Testimony on the Safety Measures Prior to the Fukushima Daiichi Accident","authors":"R. Matsui","doi":"10.3327/taesj.j20.013","DOIUrl":"https://doi.org/10.3327/taesj.j20.013","url":null,"abstract":"","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437983","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}
R. Kuwana, Daisuke Shinma, Atsushi Fushimi, Hideki Hanami, I. Hara, Hideyuki Henmi
We have developed a new pressure transmitter that reduces the signal drift effect for nuclear power plants. The drift is caused by hydrogen permeation and the radiolysis of silicone oil. The proposed method uses palladium, a hydrogen absorbing material, to suppress the drift due to hydrogen accumulation. The drift suppression and measurement performance of the pressure transmitter with Pd installed inside was evaluated. The experimental results in an environment equivalent to an actu-al plant operated for 10 years indicate that the amount of drift in the pressure transmitter with Pd was below the detection limit （＋ 0.01 kPa ） . The maximum error in the input / output characteristics was 0.16 ％ , the error due to vibration was within ± 0.1 ％ , and the step response was 1.1 s or less. In the experiment of this research, it was confirmed that all relevant values were within those of the tar get performance.
{"title":"Evaluation of Hydrogen Accumulation Suppression and Measurement Performance for Pressure Transmitter Using Palladium","authors":"R. Kuwana, Daisuke Shinma, Atsushi Fushimi, Hideki Hanami, I. Hara, Hideyuki Henmi","doi":"10.3327/taesj.j20.020","DOIUrl":"https://doi.org/10.3327/taesj.j20.020","url":null,"abstract":"We have developed a new pressure transmitter that reduces the signal drift effect for nuclear power plants. The drift is caused by hydrogen permeation and the radiolysis of silicone oil. The proposed method uses palladium, a hydrogen absorbing material, to suppress the drift due to hydrogen accumulation. The drift suppression and measurement performance of the pressure transmitter with Pd installed inside was evaluated. The experimental results in an environment equivalent to an actu-al plant operated for 10 years indicate that the amount of drift in the pressure transmitter with Pd was below the detection limit （＋ 0.01 kPa ） . The maximum error in the input / output characteristics was 0.16 ％ , the error due to vibration was within ± 0.1 ％ , and the step response was 1.1 s or less. In the experiment of this research, it was confirmed that all relevant values were within those of the tar get performance.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437563","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 purpose of this paper is to clarify the true cause of the Fukushima meltdown accident from the viewpoint of reactor design. There are only two factors. One is that a total loss of battery power was not considered in the basic design, and the other is that the fail-close design was selected in longterm core cooling systems, as the confine function was preferred over the cool function in the three safety functions of stop (nuclear reaction), cool (decay heat) and confine (radioactivity) in the basic criteria. After the loss of all power (battery and station power) in Unit 1, the IC system failed because of the fail-close design. After the loss of all power in Unit 2, the core-cooling function of the RCIC system failed because of the instability of two-phase flow in the turbine steam line, since the core decay heat was confined in the reactor and containment vessel owing to the fail-close design of the vent valves. As loss of station power occurred but battery power was available in Unit 3, operators were able to activate the RCIC system, which was tripped by the trip signal after one day. Then, the HPCI system was started automatically but stopped after about 10 hours because of the loss of battery power. After the loss of core cooling, core meltdown occurred in Units 1 to 3. The lessons learned from this accident are that the core-cooling system should be designed to withstand the loss of all power in its basic design and that the cool function should be preferred over the confine function.
{"title":"True cause of Fukushima Meltdown Accident New Analysis about Loss of Core Cooling Based on Latest Data","authors":"Tsuyoshi Matsuoka","doi":"10.3327/TAESJ.J20.029","DOIUrl":"https://doi.org/10.3327/TAESJ.J20.029","url":null,"abstract":"The purpose of this paper is to clarify the true cause of the Fukushima meltdown accident from the viewpoint of reactor design. There are only two factors. One is that a total loss of battery power was not considered in the basic design, and the other is that the fail-close design was selected in longterm core cooling systems, as the confine function was preferred over the cool function in the three safety functions of stop (nuclear reaction), cool (decay heat) and confine (radioactivity) in the basic criteria. After the loss of all power (battery and station power) in Unit 1, the IC system failed because of the fail-close design. After the loss of all power in Unit 2, the core-cooling function of the RCIC system failed because of the instability of two-phase flow in the turbine steam line, since the core decay heat was confined in the reactor and containment vessel owing to the fail-close design of the vent valves. As loss of station power occurred but battery power was available in Unit 3, operators were able to activate the RCIC system, which was tripped by the trip signal after one day. Then, the HPCI system was started automatically but stopped after about 10 hours because of the loss of battery power. After the loss of core cooling, core meltdown occurred in Units 1 to 3. The lessons learned from this accident are that the core-cooling system should be designed to withstand the loss of all power in its basic design and that the cool function should be preferred over the confine function.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437641","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}
We measured count rates and air dose rates at 11 measurement points little affected by the influ ence of the Fukushima Dai-ichi nuclear power plant accident to obtain parameters for a background equation applying KURAMA - II loaded with the high sensitivity CsI （ Tl ） detector, C12137 - 01. It was found that the sensitivity of KURAMA - II loaded with C12137 - 01 was about 10 times or more for background measurement, compared with KURAMA - II loaded with the standard CsI （ Tl ） detector, C12137. The background equation for the energy range of 1400 - 2000 keV was determined to be y （ µSv / h ）＝ 0.062 x （ cps ） . We evaluated background air dose rates using KURAMA - II loaded with C12137 - 01 for 71 municipalities and compared them with the results of a previous study of using KURAMA - II loaded with C12137. Evaluated background air dose rates in this study were almost equal to those in the previous study. We confirmed that the background equation evaluated in this study was applicable for KURAMA - II loaded with C12137 - 01.
{"title":"Determination of Parameters for an Equation to Obtain Natural Background Radiation Using KURAMA-II Loaded with C12137-01 CsI(Tl) Detector","authors":"M. Andoh, N. Matsuda, Kimiaki Saito","doi":"10.3327/TAESJ.J20.007","DOIUrl":"https://doi.org/10.3327/TAESJ.J20.007","url":null,"abstract":"We measured count rates and air dose rates at 11 measurement points little affected by the influ ence of the Fukushima Dai-ichi nuclear power plant accident to obtain parameters for a background equation applying KURAMA - II loaded with the high sensitivity CsI （ Tl ） detector, C12137 - 01. It was found that the sensitivity of KURAMA - II loaded with C12137 - 01 was about 10 times or more for background measurement, compared with KURAMA - II loaded with the standard CsI （ Tl ） detector, C12137. The background equation for the energy range of 1400 - 2000 keV was determined to be y （ µSv / h ）＝ 0.062 x （ cps ） . We evaluated background air dose rates using KURAMA - II loaded with C12137 - 01 for 71 municipalities and compared them with the results of a previous study of using KURAMA - II loaded with C12137. Evaluated background air dose rates in this study were almost equal to those in the previous study. We confirmed that the background equation evaluated in this study was applicable for KURAMA - II loaded with C12137 - 01.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437533","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. Mikami, Hiroyuki Tanaka, Naotoshi Okuda, R. Sakamoto, Kotaro Ochi, Kiichiro Uno, N. Matsuda, Kimiaki Saito
To determine the background radiation level in an area affected by the Fukushima Daiichi nuclear power plant accident in 2011, natural terrestrial gamma rays had been measured using portable germanium detectors repeatedly from 2013 through 2019, at 370 locations within an area of 80 km radius around the Fukushima Daiichi nuclear power plant. At these locations, radioactive 238 U, 232 Th, and 40 K concentrations in soil and air kerma rates at a height of 1 m above the ground due to terrestrial gamma rays were obtained by the method indicated in ICRU report 53. The average 238 U, 232 Th, and 40 K concentrations were 18.8 （ standard deviation, SD: 6.37 ） , 22.7 （ SD: 11.7 ） , and 428 （ SD: 163 ） Bq / kg, respectively, and the average air kerma rate over the area was found to be 0.0402 （ SD: 0.0146 ） μ Gy / h. The obtained air kerma rates were compared with those reported in the literature. It was confirmed that the measured data positively correlated with each other with a regression coeffi cient close to one and agreed within a factor of two. A trend similar to that in previous findings was observed, that is, the air kerma rates at locations geologically classified as granite and rhyolite zones were statistically significantly higher than those at other locations.
{"title":"In situ spectrometry of terrestrial gamma rays using portable germanium detectors in area of 80 km radius around the Fukushima Daiichi nuclear power plant","authors":"S. Mikami, Hiroyuki Tanaka, Naotoshi Okuda, R. Sakamoto, Kotaro Ochi, Kiichiro Uno, N. Matsuda, Kimiaki Saito","doi":"10.3327/taesj.j20.010","DOIUrl":"https://doi.org/10.3327/taesj.j20.010","url":null,"abstract":"To determine the background radiation level in an area affected by the Fukushima Daiichi nuclear power plant accident in 2011, natural terrestrial gamma rays had been measured using portable germanium detectors repeatedly from 2013 through 2019, at 370 locations within an area of 80 km radius around the Fukushima Daiichi nuclear power plant. At these locations, radioactive 238 U, 232 Th, and 40 K concentrations in soil and air kerma rates at a height of 1 m above the ground due to terrestrial gamma rays were obtained by the method indicated in ICRU report 53. The average 238 U, 232 Th, and 40 K concentrations were 18.8 （ standard deviation, SD: 6.37 ） , 22.7 （ SD: 11.7 ） , and 428 （ SD: 163 ） Bq / kg, respectively, and the average air kerma rate over the area was found to be 0.0402 （ SD: 0.0146 ） μ Gy / h. The obtained air kerma rates were compared with those reported in the literature. It was confirmed that the measured data positively correlated with each other with a regression coeffi cient close to one and agreed within a factor of two. A trend similar to that in previous findings was observed, that is, the air kerma rates at locations geologically classified as granite and rhyolite zones were statistically significantly higher than those at other locations.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437544","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 the long-term energy supply and demand outlook, the energy mix has become a global trend, and nuclear power plants （ NPPs ） are required to maintain a certain power ratio over a long period in Japan. Under such circumstances and with the energy mix, the long-term operation （ LTO ） of existing NPPs is attracting attention. LTO requires proper management during the operation period of the NPP, including decommissioning; this is plant life management （ PLM ） . In this study, we will take up PLM, which is an activity performed to realize LTO, give an overview of the current situation in Japan, and present performance indicators to measure its effectiveness. As a result, it becomes clear that a continuous improvement can be observed by adding a time axis to the form of knowledge that has been considered thus far. Furthermore, regarding the reduction in the number of accidental fail-ures, which is the remaining issue related to physical deterioration, technical and organizational as-pects will be discussed as countermeasures, and solutions will be presented along with a systematic diagram of knowledge management.
{"title":"A Study of Knowledge Management on Enhancing the Effectiveness of Plant Life Management for Nuclear Power Plants","authors":"Hideo Tanaka, N. Sekimura","doi":"10.3327/taesj.j20.024","DOIUrl":"https://doi.org/10.3327/taesj.j20.024","url":null,"abstract":"In the long-term energy supply and demand outlook, the energy mix has become a global trend, and nuclear power plants （ NPPs ） are required to maintain a certain power ratio over a long period in Japan. Under such circumstances and with the energy mix, the long-term operation （ LTO ） of existing NPPs is attracting attention. LTO requires proper management during the operation period of the NPP, including decommissioning; this is plant life management （ PLM ） . In this study, we will take up PLM, which is an activity performed to realize LTO, give an overview of the current situation in Japan, and present performance indicators to measure its effectiveness. As a result, it becomes clear that a continuous improvement can be observed by adding a time axis to the form of knowledge that has been considered thus far. Furthermore, regarding the reduction in the number of accidental fail-ures, which is the remaining issue related to physical deterioration, technical and organizational as-pects will be discussed as countermeasures, and solutions will be presented along with a systematic diagram of knowledge management.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437582","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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