A radiation monitoring system using unmanned aerial vehicles (UAVs) was developed for post-nuclear accidents by the Korea Institute of Nuclear Safety (KINS). The Japan Atomic Energy Agency (JAEA) has been conducted radiation monitoring in the Fukushima area and undertaking research and development of related technology. Considering future large-scale disasters, it is important that measurement methods using UAVs are unified between the neighbor countries. Two organizations in neighbor countries attempted technical collaborations to compare results obtained from different methods. In 2015, measurements were carried out in an area within 10 km from the Fukushima Dai-ichi Nuclear Power Station (FDNPS), where an accident occurred due to the Great East Japan Earthquake and where contamination remains and access is controlled. Corrections to convert the coefficients from detectors in air to the radiation dose or radioactivity concentration on the surface were carried out in areas previously surveyed as flat and relatively evenly contaminated. Explorations of contamination mapping were conducted in river basins, with contaminants appearing in different water and soil contours, which were expected to make intuitive comparisons easier for multiple mappings. We used a Japanese unmanned helicopter, which is used for agricultural applications such as the spraying of pesticides. The measurement system of JAEA and KINS was installed and the same route was flown once in each case.
{"title":"Comparison of the Fukushima radioactive mapping by two different aerial radiation monitoring systems","authors":"Byoung-Jik Kim, M. Sasaki, Y. Sanada","doi":"10.15669/PNST.6.130","DOIUrl":"https://doi.org/10.15669/PNST.6.130","url":null,"abstract":"A radiation monitoring system using unmanned aerial vehicles (UAVs) was developed for post-nuclear accidents by the Korea Institute of Nuclear Safety (KINS). The Japan Atomic Energy Agency (JAEA) has been conducted radiation monitoring in the Fukushima area and undertaking research and development of related technology. Considering future large-scale disasters, it is important that measurement methods using UAVs are unified between the neighbor countries. Two organizations in neighbor countries attempted technical collaborations to compare results obtained from different methods. In 2015, measurements were carried out in an area within 10 km from the Fukushima Dai-ichi Nuclear Power Station (FDNPS), where an accident occurred due to the Great East Japan Earthquake and where contamination remains and access is controlled. Corrections to convert the coefficients from detectors in air to the radiation dose or radioactivity concentration on the surface were carried out in areas previously surveyed as flat and relatively evenly contaminated. Explorations of contamination mapping were conducted in river basins, with contaminants appearing in different water and soil contours, which were expected to make intuitive comparisons easier for multiple mappings. We used a Japanese unmanned helicopter, which is used for agricultural applications such as the spraying of pesticides. The measurement system of JAEA and KINS was installed and the same route was flown once in each case.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"50 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75820641","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}
Radioactive Material Transport safety is an important branch of nuclear safety. In the safety evaluation for radioactive material transport package, the combination of experiment and simulation is often used. This paper studied the finite element simulation of a kind of 60Co source transport container. The situation of the package experiment and the finite element simulation method were introduced. Several different material models were used to simulate and their results were compare with the experimental data. The results showed that all the calculations were conservative and the bilinear hardening model was better for wood while bilinear hardening with failure strain model for steel. The feasibility of finite element simulation and the importance of material model were illustrated. Finally, some direction of the next step for finite element simulation was discussed.
{"title":"Simulation research on safety verification of 60Co transportation package","authors":"Dong Meng, Guoqiang Li, Jiangang Zhang, Dajie Zhuang, Renze Wang, Hongchao Sun, Shutang Sun, Xuexin Wang, Zheng-Jie Hong","doi":"10.15669/PNST.6.162","DOIUrl":"https://doi.org/10.15669/PNST.6.162","url":null,"abstract":"Radioactive Material Transport safety is an important branch of nuclear safety. In the safety evaluation for radioactive material transport package, the combination of experiment and simulation is often used. This paper studied the finite element simulation of a kind of 60Co source transport container. The situation of the package experiment and the finite element simulation method were introduced. Several different material models were used to simulate and their results were compare with the experimental data. The results showed that all the calculations were conservative and the bilinear hardening model was better for wood while bilinear hardening with failure strain model for steel. The feasibility of finite element simulation and the importance of material model were illustrated. Finally, some direction of the next step for finite element simulation was discussed.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"16 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82389867","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}
Anchang Deng, Jun Zhu, Yunfeng Shi, Chao Chen, Tian Xie, Ting Li, A. Zhang
There is a scientific support that migration data of Sr-90 in the nuclear waste landfill soil will provide for safety estimation and accident response measures in landfill.In order to make a more accurate prediction of the migration of Sr-90, it is critical to get the migration parameters such as longitudinal (or transverse) dispersivity and partition coefficient. This article try to use a method for estimating the migration parameters of Sr-90 in variable saturated soils combining experiment and numerical simulation, then explores the method with the migration of Sr-90 in silty loam in Shanxi province as an example. The migration experiment of Sr-90 was carried by column method , the water flow in is 375 mL/d, the pH value was about 7 at room temperature. The results show that the migration distance of central flow direction for Sr-90 is 3.9 cm and the peak concentration is 1.04×104 Bq/cm3. According to the concentration distribution of Sr-90 in the soil column combined with three-dimensional numerical model of nuclide migration (Hydrus-3d), the partition coefficient in the silty loam is 79 ml/g while the longitudinal dispersivity is 0.7 cm and the transverse dispersivity is 0.8 cm by fitting. This method takes the porosity and water velocity of solid into consideration that static experiments fail to cover and obtains the longitudinal and transverse dispersivity at the same time, which making the results more tally with the actual situation.
{"title":"The migration experiment of Sr-90 in variable saturated soils and numerical simulation used Hydrus-3d","authors":"Anchang Deng, Jun Zhu, Yunfeng Shi, Chao Chen, Tian Xie, Ting Li, A. Zhang","doi":"10.15669/pnst.6.156","DOIUrl":"https://doi.org/10.15669/pnst.6.156","url":null,"abstract":"There is a scientific support that migration data of Sr-90 in the nuclear waste landfill soil will provide for safety estimation and accident response measures in landfill.In order to make a more accurate prediction of the migration of Sr-90, it is critical to get the migration parameters such as longitudinal (or transverse) dispersivity and partition coefficient. This article try to use a method for estimating the migration parameters of Sr-90 in variable saturated soils combining experiment and numerical simulation, then explores the method with the migration of Sr-90 in silty loam in Shanxi province as an example. The migration experiment of Sr-90 was carried by column method , the water flow in is 375 mL/d, the pH value was about 7 at room temperature. The results show that the migration distance of central flow direction for Sr-90 is 3.9 cm and the peak concentration is 1.04×104 Bq/cm3. According to the concentration distribution of Sr-90 in the soil column combined with three-dimensional numerical model of nuclide migration (Hydrus-3d), the partition coefficient in the silty loam is 79 ml/g while the longitudinal dispersivity is 0.7 cm and the transverse dispersivity is 0.8 cm by fitting. This method takes the porosity and water velocity of solid into consideration that static experiments fail to cover and obtains the longitudinal and transverse dispersivity at the same time, which making the results more tally with the actual situation.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"99 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86508376","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. Asahara, H. Hayashi, E. Tomita, K. Sakuragawa, H. Saegusa, Yasufumi Shitakubo, H. Ikushima, Y. Kanazawa, Y. Mihara, Y. Miyahara, T. Okazaki, T. Hashizume, V. Cruz
aGraduate School of Health Sciences, Tokushima University, 3-18-15, Kuramoto, Tokushima, 770-8503, Japan; bSchool of Health Sciences, Tokushima University, 3-18-15, Kuramoto, Tokushima, 770-8503, Japan; cTokushima University Hospital, 2-50-1, Kuramoto, Tokushima, 770-8503, Japan; dShimane University Hospital, 89-1, Enya, Izumo, Shimane, 693-0021, Japan; eNagase Landauer, Ltd., C22 gaiku-1, Suwa, Tsukuba, Ibaraki, 300-2686, Japan; fCollege of Medical, Pharmaceutical and Health Sciences, Kanazawa University, 5-11-80 Kodatsuno, Kanazawa, Ishikawa, 920-0942, Japan
{"title":"Development of novel rectum dosimeter using OSL sheet with the aim of direct dose measurement of organ dose during brachytherapy","authors":"T. Asahara, H. Hayashi, E. Tomita, K. Sakuragawa, H. Saegusa, Yasufumi Shitakubo, H. Ikushima, Y. Kanazawa, Y. Mihara, Y. Miyahara, T. Okazaki, T. Hashizume, V. Cruz","doi":"10.15669/PNST.6.30","DOIUrl":"https://doi.org/10.15669/PNST.6.30","url":null,"abstract":"aGraduate School of Health Sciences, Tokushima University, 3-18-15, Kuramoto, Tokushima, 770-8503, Japan; bSchool of Health Sciences, Tokushima University, 3-18-15, Kuramoto, Tokushima, 770-8503, Japan; cTokushima University Hospital, 2-50-1, Kuramoto, Tokushima, 770-8503, Japan; dShimane University Hospital, 89-1, Enya, Izumo, Shimane, 693-0021, Japan; eNagase Landauer, Ltd., C22 gaiku-1, Suwa, Tsukuba, Ibaraki, 300-2686, Japan; fCollege of Medical, Pharmaceutical and Health Sciences, Kanazawa University, 5-11-80 Kodatsuno, Kanazawa, Ishikawa, 920-0942, Japan","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"35 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88539680","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. Nakamura, K. Maehata, T. Sugimoto, Y. Kiguchi, N. Iyomoto, Y. Morishita, K. Takasaki, K. Mitsuda
aNuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken 319-1194, Japan; bDepartment of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Nishi-ku, Fukuoka-shi 819-0395, Japan; cNuclear Science Research Institute, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195, Japan; dInstitute of Space and Astronautical Science, Japan Aerospace Eploration Agency, 3-1-1 Yoshinodai, Chuo-ku, Sagamihara-shi, Kanagawa 252-5210, Japan
{"title":"Spectroscopic measurements of L X rays using a transition-edge sensor microcalorimeter for nondestructive analysis of transuranium elements","authors":"K. Nakamura, K. Maehata, T. Sugimoto, Y. Kiguchi, N. Iyomoto, Y. Morishita, K. Takasaki, K. Mitsuda","doi":"10.15669/PNST.6.8","DOIUrl":"https://doi.org/10.15669/PNST.6.8","url":null,"abstract":"aNuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-ken 319-1194, Japan; bDepartment of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Nishi-ku, Fukuoka-shi 819-0395, Japan; cNuclear Science Research Institute, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195, Japan; dInstitute of Space and Astronautical Science, Japan Aerospace Eploration Agency, 3-1-1 Yoshinodai, Chuo-ku, Sagamihara-shi, Kanagawa 252-5210, Japan","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":"76207688","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}
Kyo-Youn Kim, K. Kang, D. Keum, Bong-Hwan Kim, K. P. Kim, Byung Il Kim, S. Seo, Y. Jin, Soo-Geun Kim, H. Kim, H. Ahn, K. Cho, K. Jeong, W. Park
After the Fukushima accident and Busan district’s court ruling partially in favor of some of the plaintiffs, the residents near Nuclear Power Plants (NPPs) have suffered from ungrounded fears. To obliterate their fear and anxiety, the correlation between the occurrence of thyroid cancer and radiation from NPPs has been analyzed by experts in this paper. At a dose range of 100 mSv or below, this study suggests that there is no scientific evidence that carcinogenesis increases based on the radiation dose. In conclusion, no causal relation has been shown between NPPs and the occurrence of thyroid cancer of residents living near NPPs. Government supported research should be increased to relieve ungrounded anxiety in the future.
{"title":"Technical review of thyroid cancer effects by radiation of NPPs in Korea","authors":"Kyo-Youn Kim, K. Kang, D. Keum, Bong-Hwan Kim, K. P. Kim, Byung Il Kim, S. Seo, Y. Jin, Soo-Geun Kim, H. Kim, H. Ahn, K. Cho, K. Jeong, W. Park","doi":"10.15669/PNST.6.193","DOIUrl":"https://doi.org/10.15669/PNST.6.193","url":null,"abstract":"After the Fukushima accident and Busan district’s court ruling partially in favor of some of the plaintiffs, the residents near Nuclear Power Plants (NPPs) have suffered from ungrounded fears. To obliterate their fear and anxiety, the correlation between the occurrence of thyroid cancer and radiation from NPPs has been analyzed by experts in this paper. At a dose range of 100 mSv or below, this study suggests that there is no scientific evidence that carcinogenesis increases based on the radiation dose. In conclusion, no causal relation has been shown between NPPs and the occurrence of thyroid cancer of residents living near NPPs. Government supported research should be increased to relieve ungrounded anxiety in the future.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"98 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79260687","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}
Chewook Yim, Do-Hyun Kim, Jae Hyun Kim, Jae Yong Lee, Quang Huy Khuat, M. Woo, C. Shin, Jong Kyung Kim, Sangjin Lee, S. Nam, Jongwoo Kim, Bo Kyun Seo
Isotope Separator Online (ISOL) facility at the Institute for Basic Science (IBS) in South Korea has been designed for producing rare isotopes. The purpose of this work was to analyze the effect of the strategy on neutron source term to evaluate effective dose for ISOL target room. Several neutron source terms were generated by varying the dimensional distribution, the number of angular divisions, and the number of energy divisions. For the dimensional distribution of neutron source, a cylindrical distribution with same shape as the target was recommended in front wall and a cylinder and a point distribution were recommended in side wall. Also, more than 32 angle divisions which had within 1.5 % discrepancy both in the front and side wall was recommended for dividing angles. In a case of dividing energies, a discrepancy within 2 % was shown in the source terms divided into more than 100 divisions. However, in case that discrete energy distribution is used, the dose was highly overestimated as the number of energy divisions decreases.
{"title":"Dose assessment analysis on neutron source terms of 70 MeV proton and UC2 target reaction for RAON ISOL target system","authors":"Chewook Yim, Do-Hyun Kim, Jae Hyun Kim, Jae Yong Lee, Quang Huy Khuat, M. Woo, C. Shin, Jong Kyung Kim, Sangjin Lee, S. Nam, Jongwoo Kim, Bo Kyun Seo","doi":"10.15669/PNST.6.247","DOIUrl":"https://doi.org/10.15669/PNST.6.247","url":null,"abstract":"Isotope Separator Online (ISOL) facility at the Institute for Basic Science (IBS) in South Korea has been designed for producing rare isotopes. The purpose of this work was to analyze the effect of the strategy on neutron source term to evaluate effective dose for ISOL target room. Several neutron source terms were generated by varying the dimensional distribution, the number of angular divisions, and the number of energy divisions. For the dimensional distribution of neutron source, a cylindrical distribution with same shape as the target was recommended in front wall and a cylinder and a point distribution were recommended in side wall. Also, more than 32 angle divisions which had within 1.5 % discrepancy both in the front and side wall was recommended for dividing angles. In a case of dividing energies, a discrepancy within 2 % was shown in the source terms divided into more than 100 divisions. However, in case that discrete energy distribution is used, the dose was highly overestimated as the number of energy divisions decreases.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"47 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90612343","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}
Kotaro Ochi, M. Sasaki, Mutsushi Ishida, Y. Sanada
After the Fukushima Daiichi nuclear power plant accident, some airborne and ground radiation measurement techniques have been applied to the environmental radiation measurements. These methods have been used in different situations depending on the spatial distribution of air dose rate in the environment. In our previous studies, the most effective tool was selected in response to the feature of targeted environment. However, airborne and ground radiation measurement results have not yet been evaluated and compared in the same environment. In this study, we attempted to quantitatively evaluate the results of airborne and ground radiation measurements with the parameter of normalized mean square error in the same farm. Consequently, the reliability of each measurement technique was quantified. The comparison of different techniques, which is important to effectively monitor the spatial distribution of air dose rate in the environment, could be achieved using this method.
{"title":"Comparison of airborne and ground-based tools used for radiation measurement in the environment","authors":"Kotaro Ochi, M. Sasaki, Mutsushi Ishida, Y. Sanada","doi":"10.15669/PNST.6.103","DOIUrl":"https://doi.org/10.15669/PNST.6.103","url":null,"abstract":"After the Fukushima Daiichi nuclear power plant accident, some airborne and ground radiation measurement techniques have been applied to the environmental radiation measurements. These methods have been used in different situations depending on the spatial distribution of air dose rate in the environment. In our previous studies, the most effective tool was selected in response to the feature of targeted environment. However, airborne and ground radiation measurement results have not yet been evaluated and compared in the same environment. In this study, we attempted to quantitatively evaluate the results of airborne and ground radiation measurements with the parameter of normalized mean square error in the same farm. Consequently, the reliability of each measurement technique was quantified. The comparison of different techniques, which is important to effectively monitor the spatial distribution of air dose rate in the environment, could be achieved using this method.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"69 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81199662","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 Seok Kim, P. Lee, Byeong Ryong Park, Han Sung Kim, Kum-Bae Kim, Gyu-Seok Cho, Sehwan Shim, Wi-Ho Ha, Sunhoo Park, Y. Jin
Radio-photoluminescence glass dosimeter (RPLGD) has many advantages such as small size, high sensitivity, low fading effect, excellent dose linearity and repeatability. Because of these advantages, RPLGDs were used to measure the absorbed dose as in-vivo dosimeter. In Korea Institute of Radiological and Medical Sciences (KIRAMS), a minipig physical phantom was applied to evaluate the dose distribution for animal irradiation study. In this study, RPLGDs were used as a dosimeter to evaluate the dose distribution in the 5th and 25th slices. For the reliable result, RPLGDs were irradiated to evaluate the expanded measurement uncertainty. The expanded measurement uncertainty of RPLGD was determined as 6.08% with a coverage factor of k=2. Additionally, the framework of the Geant4 toolkit was used to verify the dose distribution by using RPLGD measurement under the same experiment condition. To analyze the linearity between the RPLGD measurements and Geant4 simulation, each of absorbed doses was compared according to the measurement points in the minipig physical phantom. As a result, the coefficients of determination (R2) were evaluated as 0.9767 and 0.9852 at each slice of the 5th and 25th.
{"title":"Measurement of radiation dose distribution in minipig physical phantom using RPLGD","authors":"Jae Seok Kim, P. Lee, Byeong Ryong Park, Han Sung Kim, Kum-Bae Kim, Gyu-Seok Cho, Sehwan Shim, Wi-Ho Ha, Sunhoo Park, Y. Jin","doi":"10.15669/PNST.6.113","DOIUrl":"https://doi.org/10.15669/PNST.6.113","url":null,"abstract":"Radio-photoluminescence glass dosimeter (RPLGD) has many advantages such as small size, high sensitivity, low fading effect, excellent dose linearity and repeatability. Because of these advantages, RPLGDs were used to measure the absorbed dose as in-vivo dosimeter. In Korea Institute of Radiological and Medical Sciences (KIRAMS), a minipig physical phantom was applied to evaluate the dose distribution for animal irradiation study. In this study, RPLGDs were used as a dosimeter to evaluate the dose distribution in the 5th and 25th slices. For the reliable result, RPLGDs were irradiated to evaluate the expanded measurement uncertainty. The expanded measurement uncertainty of RPLGD was determined as 6.08% with a coverage factor of k=2. Additionally, the framework of the Geant4 toolkit was used to verify the dose distribution by using RPLGD measurement under the same experiment condition. To analyze the linearity between the RPLGD measurements and Geant4 simulation, each of absorbed doses was compared according to the measurement points in the minipig physical phantom. As a result, the coefficients of determination (R2) were evaluated as 0.9767 and 0.9852 at each slice of the 5th and 25th.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"29 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":"88348248","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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