Criticality accident neutron dosimetry is based on measurement conducted using personal dosemeters and biological samples of persons exposed to neutrons from an accidental criticality. The authors computed the response functions of a personal dosemeter (NCL-TLD badge) and hair (sulfur) activation per unit incident neutron fluence, and established a response dataset compiled using 140 neutron spectra that are likely to be encountered in a criticality accident.
{"title":"Dataset of TLD badge response and hair activation for criticality accident neutron dosimetry","authors":"N. Tsujimura, F. Takahashi, C. Takada","doi":"10.15669/PNST.6.148","DOIUrl":"https://doi.org/10.15669/PNST.6.148","url":null,"abstract":"Criticality accident neutron dosimetry is based on measurement conducted using personal dosemeters and biological samples of persons exposed to neutrons from an accidental criticality. The authors computed the response functions of a personal dosemeter (NCL-TLD badge) and hair (sulfur) activation per unit incident neutron fluence, and established a response dataset compiled using 140 neutron spectra that are likely to be encountered in a criticality accident.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"91 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88537938","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}
V. Cruz, T. Okazaki, H. Hayashi, Y. Mihara, T. Asahara, N. Kimoto, H. Okino, Y. Kanazawa, T. Hashizume, I. Kobayashi
Radiation doses received by patients and medical staff from examinations using X-rays and radioactive materials have been increasing, and a reliable radiation dosimetry system is a necessity. An OSL dosimeter can be used and applied in such situations. However at this time, its property for nuclear medicine region is unclear. When we calculate the basic properties in this region using the Monte-Carlo simulation code, the consideration of secondary electron equilibrium is important. The aim of this study is to propose a compact irradiation system for simulation study, and use it to evaluate the energy and angular dependence of the small-type OSL dosimeter. The proposed system uses a phantom of acrylic and we examined which phantom thickness will be used considering the accuracy of the simulation and the contamination from scattered rays. Then, this system was applied to determine angular and energy dependences of the small-type OSL dosimeter. Experiments using the OSL dosimeter were performed in order to check the accuracy of the simulations. In addition when simulating the response of the OSL dosimeter, we determined the basic parameters of the detection material. We performed several situations, and concluded that the following parameters were in good agreement with the experiment: a detection layer of 100% Al2O3 with a density of 1.41 g/cm3.
{"title":"Energy and angular dependence of the small-type OSL dosimeter in nuclear medicine regions using Monte Carlo simulation","authors":"V. Cruz, T. Okazaki, H. Hayashi, Y. Mihara, T. Asahara, N. Kimoto, H. Okino, Y. Kanazawa, T. Hashizume, I. Kobayashi","doi":"10.15669/PNST.6.34","DOIUrl":"https://doi.org/10.15669/PNST.6.34","url":null,"abstract":"Radiation doses received by patients and medical staff from examinations using X-rays and radioactive materials have been increasing, and a reliable radiation dosimetry system is a necessity. An OSL dosimeter can be used and applied in such situations. However at this time, its property for nuclear medicine region is unclear. When we calculate the basic properties in this region using the Monte-Carlo simulation code, the consideration of secondary electron equilibrium is important. The aim of this study is to propose a compact irradiation system for simulation study, and use it to evaluate the energy and angular dependence of the small-type OSL dosimeter. The proposed system uses a phantom of acrylic and we examined which phantom thickness will be used considering the accuracy of the simulation and the contamination from scattered rays. Then, this system was applied to determine angular and energy dependences of the small-type OSL dosimeter. Experiments using the OSL dosimeter were performed in order to check the accuracy of the simulations. In addition when simulating the response of the OSL dosimeter, we determined the basic parameters of the detection material. We performed several situations, and concluded that the following parameters were in good agreement with the experiment: a detection layer of 100% Al2O3 with a density of 1.41 g/cm3.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"30 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78805901","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 distribution images of α-emission nuclides in the inner organ of dried sea fish such as sardine were obtained with nuclear track detector CR-39 by exposing for about 3 months. To obtain the radioactivity density in the inner organ from the pit density on the surface of CR-39, the detection efficiency of α-particle emitted in the organ was obtained by the calculation of energy loss of α-particles in the organ and in CR-39 using Bethe formula. The radioactivity densities were 1.3 Bq/cm3 and 85 Bq/cm3 for sardine and the liver of golden threadfin bream, respectively, and the energy absorption doses were 33 mGy/y and 2.2 Gy/y, respectively.
{"title":"Po-210 distribution image and radioactivity determination in inner organ of fish with nuclear track detector CR-39","authors":"C. Mori","doi":"10.15669/PNST.6.243","DOIUrl":"https://doi.org/10.15669/PNST.6.243","url":null,"abstract":"The distribution images of α-emission nuclides in the inner organ of dried sea fish such as sardine were obtained with nuclear track detector CR-39 by exposing for about 3 months. To obtain the radioactivity density in the inner organ from the pit density on the surface of CR-39, the detection efficiency of α-particle emitted in the organ was obtained by the calculation of energy loss of α-particles in the organ and in CR-39 using Bethe formula. The radioactivity densities were 1.3 Bq/cm3 and 85 Bq/cm3 for sardine and the liver of golden threadfin bream, respectively, and the energy absorption doses were 33 mGy/y and 2.2 Gy/y, respectively.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"26 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74900921","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}
M. Kowatari, Y. Tanimura, P. Kessler, S. Neumaier, A. Roettger
The simultaneous evaluation of dose rate and radioactivity using newly developed scintillation detectors, i.e. CeBr3 and SrI2(Eu) was invesigated for environmental radiation measurement. Energy dependence and linearity of both detectors were verified by measurements in a low backgrould laboratory operated by the German metrological insititute and found to be applicable to enviromental monitoring purposes. As a result of environmental gamma ray measurements in normal situation, evaluated air kerma rate and radioactivity in/on soil for 137Cs, 134Cs and 40K seemed consistent. Results also support that the method developed in this study is reliable and would be applicable to the environmental radiation measurement.
{"title":"Development of a simultaneous evaluation method of radioactivity in soil and dose rate using CeBr3 and SrI2(Eu) scintillation detectors for environmental monitoring","authors":"M. Kowatari, Y. Tanimura, P. Kessler, S. Neumaier, A. Roettger","doi":"10.15669/PNST.6.81","DOIUrl":"https://doi.org/10.15669/PNST.6.81","url":null,"abstract":"The simultaneous evaluation of dose rate and radioactivity using newly developed scintillation detectors, i.e. CeBr3 and SrI2(Eu) was invesigated for environmental radiation measurement. Energy dependence and linearity of both detectors were verified by measurements in a low backgrould laboratory operated by the German metrological insititute and found to be applicable to enviromental monitoring purposes. As a result of environmental gamma ray measurements in normal situation, evaluated air kerma rate and radioactivity in/on soil for 137Cs, 134Cs and 40K seemed consistent. Results also support that the method developed in this study is reliable and would be applicable to the environmental radiation measurement.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"189 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74438866","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}
This study developed a fiber-optic radiation sensor (FORS) to make real-time measurement of gammaradiation at the nuclear facility decommissioned site. The FORS consisted of a sensing probe, a transmitting plastic optical fiber, a measuring device and a laptop computer. The sensing probe of the FORS was hexahedron form and fabricated using LYSO:Ce inorganic scintillator, mixture of epoxy and hardener as light guide, and aluminum foil as a reflector. Two sensing probes with different heights, 0.3 mm and 15 mm, were prepared. The light transmitted through the plastic optical fiber was converted by the photomultiplier tube and amplified by an amplifier. A multi-channel analyzer (MCA) with the GENIE2000 program was used for the data acquisition and analysis. The FORSs were applied to measure a Co-60 disk source (92.43 μCi, 2015.02). The measurements showed that the sensing probe with the height of 15 mm was better in terms of detection efficiency.
{"title":"Comparison between the measurements by the fiber-optic gamma radiation sensors with the sensing probes of different height","authors":"Sang Bin Lee, Jae Wook Kim, Rinah Kim, J. Moon","doi":"10.15669/PNST.6.99","DOIUrl":"https://doi.org/10.15669/PNST.6.99","url":null,"abstract":"This study developed a fiber-optic radiation sensor (FORS) to make real-time measurement of gammaradiation at the nuclear facility decommissioned site. The FORS consisted of a sensing probe, a transmitting plastic optical fiber, a measuring device and a laptop computer. The sensing probe of the FORS was hexahedron form and fabricated using LYSO:Ce inorganic scintillator, mixture of epoxy and hardener as light guide, and aluminum foil as a reflector. Two sensing probes with different heights, 0.3 mm and 15 mm, were prepared. The light transmitted through the plastic optical fiber was converted by the photomultiplier tube and amplified by an amplifier. A multi-channel analyzer (MCA) with the GENIE2000 program was used for the data acquisition and analysis. The FORSs were applied to measure a Co-60 disk source (92.43 μCi, 2015.02). The measurements showed that the sensing probe with the height of 15 mm was better in terms of detection efficiency.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"48 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88791846","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 leakage radiation dose from medical linac systems must be suppressed to prevent public exposure to radiation. Therefore, leakage dose through ducts or sleeves installed in shielding walls need to be evaluated because radiation can pass through these without undergoing scattering or attenuation. However, conventional methods for calculating radiation streaming have not been sufficiently evaluated for the leakage dose from the ducts in mazes. In this study, the method provided by the Japan Radiological Society for neutrons and X-rays, Nakamura and Uwamino’s formula for neutrons, the method described by the IAEA Safety Reports Series No.47 and the method given by McGinley for X-rays were evaluated by comparing the results with a Monte Carlo calculation using MCNP5 in calculation models. The rectangular ducts in these models were located in the maze near the entrance of linac room. Compared with MCNP5, most results for duct streaming obtained using conventional methods for neutrons were within a factor of 2, whereas the results of methods using X-rays were more than a factor of 2. The results for maze streaming using Nakamura and Uwamino’s formula were in good agreement and differed by not more than 16%. Furthermore, the ratios of the X-ray dose at the duct entrance to that at the exit were calculated to investigate X-ray duct streaming with the results of MCNP5 and showed the relationships against the ratio of the opening area of the duct to square length.
{"title":"A study on calculation method of duct streaming from medical linac rooms","authors":"T. Noto, K. Kosako, Takashi Nakamura","doi":"10.15669/PNST.6.212","DOIUrl":"https://doi.org/10.15669/PNST.6.212","url":null,"abstract":"The leakage radiation dose from medical linac systems must be suppressed to prevent public exposure to radiation. Therefore, leakage dose through ducts or sleeves installed in shielding walls need to be evaluated because radiation can pass through these without undergoing scattering or attenuation. However, conventional methods for calculating radiation streaming have not been sufficiently evaluated for the leakage dose from the ducts in mazes. In this study, the method provided by the Japan Radiological Society for neutrons and X-rays, Nakamura and Uwamino’s formula for neutrons, the method described by the IAEA Safety Reports Series No.47 and the method given by McGinley for X-rays were evaluated by comparing the results with a Monte Carlo calculation using MCNP5 in calculation models. The rectangular ducts in these models were located in the maze near the entrance of linac room. Compared with MCNP5, most results for duct streaming obtained using conventional methods for neutrons were within a factor of 2, whereas the results of methods using X-rays were more than a factor of 2. The results for maze streaming using Nakamura and Uwamino’s formula were in good agreement and differed by not more than 16%. Furthermore, the ratios of the X-ray dose at the duct entrance to that at the exit were calculated to investigate X-ray duct streaming with the results of MCNP5 and showed the relationships against the ratio of the opening area of the duct to square length.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87906960","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 electron accelerator facility, neutron production induced by high energy electron above 1 GeV hitting on thick target, and the neutron deep penetration for concrete shielding can be calculated by the Jenkins formula. In the formula, the neutron source term is divided into three energy regions of GR, MID, and HE, and neutron deep penetration is solved by summing up the attenuation of the three individual source terms with different attenuation length. In this study, the concept of Jenkins formula is verified by using recent Monte Carlo codes with evaluated data and cross sections, and some parameters of Jenkins formula are revised.
{"title":"A revised Jenkins formula for electron induced neutron deep penetration calculation","authors":"H. Iwase, Y. Namito, H. Hirayama","doi":"10.15669/PNST.6.255","DOIUrl":"https://doi.org/10.15669/PNST.6.255","url":null,"abstract":"In electron accelerator facility, neutron production induced by high energy electron above 1 GeV hitting on thick target, and the neutron deep penetration for concrete shielding can be calculated by the Jenkins formula. In the formula, the neutron source term is divided into three energy regions of GR, MID, and HE, and neutron deep penetration is solved by summing up the attenuation of the three individual source terms with different attenuation length. In this study, the concept of Jenkins formula is verified by using recent Monte Carlo codes with evaluated data and cross sections, and some parameters of Jenkins formula are revised.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"6 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83433802","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}
Jae Yong Lee, Do-Hyun Kim, Chewook Yim, Jae Hyun Kim, M. Woo, Quang Huy Khuat, C. Shin, Jong Kyung Kim, Bo Kyun Seo, Ji Seok Kim
In a facility using neutron, it is important to figure out the spatial distribution of the neutron beam. To get neutron spatial distributions, multiple activation foils are used in the activation foil method. To measure the radioactivity of foils efficiently, a novel measurement system with gamma camera was proposed. The radioactivity of foils was obtained as the image form in the system. To determine the radioactivity of each foil, reconstruction algorithm was necessary. In this study, a novel reconstruction algorithm suitable to the proposed system was developed. The algorithm was validated by solving two problems. By utilizing the developed algorithm, accurate determination of radioactivity of multiple foils was possible. It is expected that the developed algorithm could be used for the efficient measurement of neutron beam distribution.
{"title":"Development of reconstruction algorithm for activation sample measurement using gamma camera","authors":"Jae Yong Lee, Do-Hyun Kim, Chewook Yim, Jae Hyun Kim, M. Woo, Quang Huy Khuat, C. Shin, Jong Kyung Kim, Bo Kyun Seo, Ji Seok Kim","doi":"10.15669/PNST.6.234","DOIUrl":"https://doi.org/10.15669/PNST.6.234","url":null,"abstract":"In a facility using neutron, it is important to figure out the spatial distribution of the neutron beam. To get neutron spatial distributions, multiple activation foils are used in the activation foil method. To measure the radioactivity of foils efficiently, a novel measurement system with gamma camera was proposed. The radioactivity of foils was obtained as the image form in the system. To determine the radioactivity of each foil, reconstruction algorithm was necessary. In this study, a novel reconstruction algorithm suitable to the proposed system was developed. The algorithm was validated by solving two problems. By utilizing the developed algorithm, accurate determination of radioactivity of multiple foils was possible. It is expected that the developed algorithm could be used for the efficient measurement of neutron beam distribution.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"2 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89468719","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. Oyama, H. Iwase, A. Toyoda, Naoto Yoshihara, T. Sanami
The thermal neutron flux distribution formed in the KEK electron/positron injector linac (KEK-linac) tunnel by the positron production beam operation was measured using a gold foil activation technique. The measured data were compared with the calculation results of the PHITS code. The data indicate that the thermal neutrons were locally distributed within a range of 15-20 m of the target position. The thermal neutron flux obtained using the PHITS code reproduced the experimental data at the target location. We obtained coefficient “C” for KEK-linac tunnel from experimental result and calculation as 2.25 that is used in empirical formula to obtain thermal neutron flux, φth = C Q / S, where Q is neutron source intensity, S is the area of tunnel surface.
利用金箔活化技术测量了KEK电子/正电子注入直线加速器(KEK-linac)隧道中正电子产生束操作形成的热中子通量分布。实测数据与PHITS规范的计算结果进行了比较。数据表明，热中子局部分布在目标位置15 ~ 20 m范围内。利用PHITS代码获得的热中子通量再现了目标位置的实验数据。根据实验结果和计算得出kek -直线隧道的系数C为2.25，φth = C Q / S，其中Q为中子源强度，S为隧道表面面积。
{"title":"Thermal neutron distribution in the beam line tunnel of the KEK electron/positron injector linac","authors":"T. Oyama, H. Iwase, A. Toyoda, Naoto Yoshihara, T. Sanami","doi":"10.15669/PNST.6.181","DOIUrl":"https://doi.org/10.15669/PNST.6.181","url":null,"abstract":"The thermal neutron flux distribution formed in the KEK electron/positron injector linac (KEK-linac) tunnel by the positron production beam operation was measured using a gold foil activation technique. The measured data were compared with the calculation results of the PHITS code. The data indicate that the thermal neutrons were locally distributed within a range of 15-20 m of the target position. The thermal neutron flux obtained using the PHITS code reproduced the experimental data at the target location. We obtained coefficient “C” for KEK-linac tunnel from experimental result and calculation as 2.25 that is used in empirical formula to obtain thermal neutron flux, φth = C Q / S, where Q is neutron source intensity, S is the area of tunnel surface.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"115 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79356652","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. Hayashi, E. Tomita, S. Goto, N. Kimoto, Keiji Tada, Ryosuke Kasai, Y. Kanazawa, Y. Mihara, T. Asahara, T. Okazaki, T. Hashizume, V. Cruz
aGraduate School of Health Sciences, Tokushima University, 3-18-15 Kuramoto, Tokushima, Japan; bSchool of Health Sciences, Tokushima University, 3-18-15 Kuramoto, Tokushima, Japan; cShimane University Faculty of Medicine, 89-1 Enya, Izumo, Shimane, Japan; dTokushima University Hospital, 3-18-15 Kuramoto, Tokushima, Japan; eNagase Landauer, Ltd., Block C22-1, Suwa, Tsukuba, Ibaraki, Japan; fpresent address: College of Medical, Pharmaceutical and Health Sciences, Kanazawa University, 5-11-80 Kodatsuno, Kanazawa, Japan
{"title":"Direct dose measurement of patients during pediatric computed tomography examination","authors":"H. Hayashi, E. Tomita, S. Goto, N. Kimoto, Keiji Tada, Ryosuke Kasai, Y. Kanazawa, Y. Mihara, T. Asahara, T. Okazaki, T. Hashizume, V. Cruz","doi":"10.15669/PNST.6.18","DOIUrl":"https://doi.org/10.15669/PNST.6.18","url":null,"abstract":"aGraduate School of Health Sciences, Tokushima University, 3-18-15 Kuramoto, Tokushima, Japan; bSchool of Health Sciences, Tokushima University, 3-18-15 Kuramoto, Tokushima, Japan; cShimane University Faculty of Medicine, 89-1 Enya, Izumo, Shimane, Japan; dTokushima University Hospital, 3-18-15 Kuramoto, Tokushima, Japan; eNagase Landauer, Ltd., Block C22-1, Suwa, Tsukuba, Ibaraki, Japan; fpresent address: College of Medical, Pharmaceutical and Health Sciences, Kanazawa University, 5-11-80 Kodatsuno, Kanazawa, Japan","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"490 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76384466","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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