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Takeda, Takeshi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 67(7), p.407 - 410, 2025/07
no abstracts in English
Takeda, Takeshi; Shibata, Taiju
JAEA-Review 2024-040, 29 Pages, 2024/09
JAEA-Review-2024-040.pdf:1.33MB
An important theme of Japan's 6th strategic energy plan is to indicate the energy policy path towards carbon neutrality by 2050. Policy responses for Japan's nuclear energy research and development (R&D) towards 2030 contain the demonstrations of technologies for small modular reactors (SMRs) through international cooperation by 2030. In light of this energy plan, basic policy initiatives over the next 10 years have been compiled to realize Green Transformation (GX), which simultaneously achieves decarbonization and economic growth. Looking overseas, activities of SMR R&D are active internationally, mainly in the US, Canada, Europe, China, and Russia. These activities are not only by heavy industry manufactures and R&D institutes, but also by venture companies. Under these circumstances, the NEA CSNI has gathered an Expert Group on SMRs (EGSMR) to help estimate the safety effects of SMRs. The EGSMR efforts required the submission of responses to several questionnaires whose main purpose was to collect the latest information on the efforts of SMR deployment and research. The first author of this report responded to this based on information from Hitachi-GE Nuclear Energy, Ltd. and Mitsubishi Heavy Industries, Ltd. as well as JAEA. Most of the responses from Japan to the questionnaires are the information that serves as the basis of CSNI Technical Opinion Paper No. 21 (TOP-21). In this report, the Japan's publicly available responses to the questionnaires arranged and additional information are explained, which complements some of the content of the TOP-21. In this manner, the investigation results of R&D related to SMR in Japan, focusing on the EGSMR activities (2022-2023), are summarized. The target of this report is to provide useful information for future discussions on international cooperation concerning SMR as well as nuclear power field human resources development internationally and domestically.
Hirayama, Hideo*; Kawasaki, Masatsugu; Matsumura, Hiroshi*; Okura, Takehisa; Namito, Yoshihito*; Sanami, Toshiya*; Taki, Mitsumasa; Oishi, Tetsuya; Yoshizawa, Michio
Insights Concerning the Fukushima Daiichi Nuclear Accident, Vol.4; Endeavors by Scientists, p.295 - 307, 2021/10
-ray exposure buildup factorsMatsuda, Norihiro; Onishi, Seiki*; Sakamoto, Yukio*; Nobuhara, Fumiyoshi*
Heisei 29-Nendo Kani Shahei Kaiseki Kodo Rebyu Wakingu Gurupu Katsudo Hokokusho (Internet), p.20 - 28, 2018/08
no abstracts in English
I concentrations in the air from pulse-height distribution observed by NaI(Tl) detector in monitoring postsYamada, Junya; Hashimoto, Makoto; Seya, Natsumi; Haba, Risa; Muto, Yasunobu; Shimizu, Takehiko; Takasaki, Koji; Yokoyama, Sumi*; Shimo, Michikuni*
Radioisotopes, 65(10), p.403 - 408, 2016/10
The purpose of this study is to develop a quick method for estimation of I concentrations in the air using data measured by monitoring posts. In this method, I concentrations were estimated by multiplying I count rates at the full-energy peak measured with a NaI(Tl) detector by a concentration conversion factor. The concentration conversion factor for monitoring posts in JAEA Oarai Center was calculated with an EGS5 Monte Carlo code. As a result, the concentration conversion factor for an infinite-air-source was 25.7 Bq/m
/cps.
Hirayama, Hideo*; Kawasaki, Masatsugu; Matsumura, Hiroshi*; Okura, Takehisa; Namito, Yoshihito*; Sanami, Toshiya*; Taki, Mitsumasa; Oishi, Tetsuya; Yoshizawa, Michio
Nihon Genshiryoku Gakkai Wabun Rombunshi, 13(3), p.119 - 126, 2014/09
A method of deducing the I-131 concentration in a radioactive plume from the time history of peak count rates determined from pulse height spectra obtained from an NaI(Tl)scintillation detector employed as a detector of a monitoring post was presented. The concentrations of I-131 in the plumes were estimated from the count rates using the calculated response of the NaI(Tl) detector with egs5 for a model of a plume uniformly containing I-131. This method was applied to the data from the monitoring posts at Nuclear Science Research Institutes of Japan Atomic Energy Agency (JAEA). The estimated time history variation of I-131 concentrations in plumes was in fair agreement with those measured directly by an air sampling method. The difference was less than a factor of 4 for plumes that arrived on March 15 and March 21, indicating relatively high I-131 concentrations among the plumes studied in this work.
Kinase, Sakae; Takagi, Shunji*; Noguchi, Hiroshi; Saito, Kimiaki
Radiation Protection Dosimetry, 125(1-4), p.189 - 193, 2007/07
Times Cited Count：17 Percentile：71.47(Environmental Sciences)In the Japan Atomic Energy Research Institute (JAERI), a calculation code -UCWBC code- for whole-body counter calibrations using voxel phantoms has been developed as an EGS4 Monte Carlo user code. To validate the UCWBC code for calibrating whole-body counters in JAERI, response functions and counting efficiencies of a p-type high-purity Ge semiconductor detector used for the whole-body counter were evaluated for a water-filled block-shape phantom by the UCWBC code and were measured by experiments. Furthermore, counting efficiencies of the Ge semiconductor detector for the male and female voxel phantoms developed in JAERI were evaluated in the photon energy range 60-1836 keV by the UCWBC code in order to examine the differences between the counting efficiencies for voxel phantoms. In conclusion, it was found that the response functions and counting efficiencies of the Ge semiconductor detector by the UCWBC code for the water-filled block-shape phantom are in good agreement with measured data. The UCWBC code was validated by the comparisons.
Liu, J. C.*; Fasso, A.*; Prinz, A.*; Rokni, S.*; Asano, Yoshihiro
Radiation Protection Dosimetry, 116(1-4), p.658 - 661, 2005/12
Times Cited Count：8 Percentile：46.92(Environmental Sciences)no abstracts in English
Kinase, Sakae
KEK Proceedings 2005-3, p.292 - 297, 2005/06
The EGS4 code was used for evaluating the absorbed fraction per unit mass of the target organ-specific absorbed fraction (SAF)- and the mean absorbed dose to the target organ per unit cumulated activity in the source organ (S value) for internal dosimetry. The SAFs and S values were evaluated on a mathematical phantom (MIRD 5 type phantom) and Japanese adult voxel phantoms (Otoko and Onago phantoms) developed at the Japan Atomic Energy Research Institute (JAERI). The evaluated SAFs and S values were compared with several published data in order to demonstrate the use of the EGS4 code for the internal dosimetry and investigate the influence of certain parameters, such as the organ masses, on SAFs and S values. It was demonstrated that the EGS4 code is useful in the evaluation of the SAFs and S values for the internal dosimetry. It was also found that the SAFs and S values for organ self-absorption depend on the organ masses and would be affected by differences in the structure of the human body.
Hakoda, Teruyuki; Hanaya, Hiroaki; Kaneko, Hirohisa; Miyashita, Atsumi; Kojima, Takuji
Radioisotopes, 54(6), p.161 - 168, 2005/06
no abstracts in English
Sakurai, Kiyoshi
Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.233 - 244, 2004/12
Whole evaluation and closing talk at the third Monte Carlo simulation symposium held on June 7-8(2004) are described.
Kinase, Sakae; Takagi, Shunji*; Noguchi, Hiroshi; Saito, Kimiaki
Proceedings of 11th International Congress of the International Radiation Protection Association (IRPA-11) (CD-ROM), 7 Pages, 2004/05
The present study was performed to validate the UCWBC code for calibrating in vivo measurements. Furthermore, the calibration data for the adult voxel phantoms developed in JAERI were evaluated by the UCWBC code in order to examine the differences between the calibration data for voxel phantoms, including a voxel version of water-filled block-shape phantom based on an actual phantom that is used for the calibration of the whole-body counter in JAERI. It was found that the calculated calibration data by the UCWBC code for the water-filled block-shape phantom show good agreement with measured ones. Consequently, the UCWBC code was validated by the comparisons. It was also found that the calibration data depend on phantoms of different sizes and the effective distance between phantom and detector. The calibration of in vivo measurements using voxel phantoms for individuals would be quite useful for the improvement in accuracy of the measurement results.
Kinase, Sakae; Zankl, M.*; Funabiki, Jun*; Noguchi, Hiroshi; Saito, Kimiaki
KEK Proceedings 2003-15, p.45 - 52, 2004/02
no abstracts in English
ray detection systemsOishi, Tetsuya
RIST News, (36), p.12 - 20, 2003/10
no abstracts in English
Kinase, Sakae; Zankl, M.*; Kuwabara, Jun; Sato, Kaoru; Noguchi, Hiroshi; Funabiki, Jun*; Saito, Kimiaki
Radiation Protection Dosimetry, 105(1-4), p.557 - 563, 2003/09
Times Cited Count：29 Percentile：84.40(Environmental Sciences)There exists a need to calculate specific absorbed fractions (SAFs) in voxel phantoms for internal dosimetry. For this purpose, an EGS4 user code for calculating SAFs using voxel phantoms was developed on the basis of an existing EGS4 user code for external dosimetry (UCPIXEL). In the developed code, the transport of photons, electrons and positrons in voxel phantoms can be simulated, particularly the transport simulations of secondary electrons in voxel phantoms can be made. The evaluated SAFs for the GSF Child voxel phantom using the developed code were found to be in good agreement with the GSF evaluated data. In addition, SAFs in adult voxel phantoms developed at JAERI were evaluated using the developed code and were compared with several published data. It was found that SAFs for organ self-absorption depend on the organ masses and would be affected by differences in the structure of the human body.
Kinase, Sakae; Noguchi, Hiroshi; Nakamura, Takashi*
Radiation Protection Dosimetry, 105(1-4), p.467 - 472, 2003/09
Times Cited Count：4 Percentile：30.47(Environmental Sciences)To calibrate a whole-body counter, it is necessary to find a determination method for peak efficiencies of detectors that the whole-body counter has. For the purpose, peak efficiencies of a Ge semi-conductor detector for point sources and volume sources were evaluated in the photon energy range of 60-1,836 keV by Monte Carlo simulation and experiment. It was found that the calculated peak efficiency curves as a function of energy without modeling the actual sensitive region of the detector are similar in shape to those measured. The calculated peak efficiencies of the detector that has an apparent dead layer (1mm) were also found to agree with the experimental values. Consequently, the simulation method for peak efficiencies was validated. In addition, an optimum design for a whole-body counter with Ge semi-conductor detectors was examined by simulation. This simulation enables to provide a method to determine an optimum arrangement of detectors in a whole-body counter offering a uniform response to various Cs-137 distributions in a human body.
-ray detection systemsOishi, Tetsuya; Tsutsumi, Masahiro; Sugita, Takeshi*; Yoshida, Makoto
Journal of Nuclear Science and Technology, 40(6), p.441 - 445, 2003/06
Times Cited Count：1 Percentile：10.38(Nuclear Science & Technology)An EGS4 user code has been developed to design and optimize ray detection systems for several types of radiation sources. The code is fundamentally based on the PRESTA-CG, which is improved on the electron transport in the EGS4 and specialized for the utilization of a combinatorial geometry (CG) method. The main additional functions in the present user code are classified into two parts of the definition of radiation sources and the transport of photons. The developed user code was applied to two types of detection systems in order to demonstrate its availability. As the result, it was found that the present code allows the detailed response analysis of complicated detection systems for several sources with just a simple handling.
counting using mathematical simulationKinase, Sakae
JAERI-Research 2003-011, 104 Pages, 2003/05
JAERI-Research-2003-011.pdf:5.11MB
In the present study, a calibration technique for in vivo counting application using Monte Carlo simulation was developed. The advantage of the technique is that counting efficiency can be obtained for various shapes, sizes that is very difficult to change for phantoms. The method for the determination of counting efficiency curves as a function of energy was developed using the present technique and a physiques correction equation was derived from the relationship between parameters of correction factor and counting efficiencies of the JAERI whole-body counter. The uncertainties in body burdens of Cs-137 estimated with the JAERI whole-body counter were also investigated using the Monte Carlo simulation and measurements. Furthermore, the evaluation method of the peak efficiencies of a Ge semi-conductor detector was developed by the Monte Carlo simulation for optimum arrangement of Ge semi-conductor detectors for designing a precision whole-body counter.
counting using mathematical simulation, in JapaneseKinase, Sakae
Medical Physics, 30(5), P. 994, 2003/05
A calibration technique for in vivo counting application using Monte Carlo simulation was developed. To validate the calibration technique by calculations, the response functions and counting efficiencies of a whole-body counter installed in JAERI were evaluated using the simulation and measurements. Consequently, the calculations are in good agreement with the measurements. The uncertainties in body burdens of 137Cs estimated with the whole-body counter were also investigated using the Monte Carlo simulation and measurements. It was found that the uncertainties of body burdens estimated with the whole-body counter are strongly dependent on various sources of uncertainty such as radioactivity distribution within the body and counting statistics.
Asano, Yoshihiro; Liu, J. C.*
KEK Proceedings 2002-18, p.48 - 54, 2003/01
The light energy was not higher than soft X-rays so that the radiation safety for synchrotron radiation passed for unworthy issues of attention. With constructing and operating the third generation facilities such as SPring-8, however, high energy synchrotron radiation of extremely high intense is available, and high accuracy should be required in the shielding and safety design for the beam of synchrotron radiation. Furthermore, the middle size facilities such as CLS (Canadian Light Source) are now under construction and the optimum design of shielding is desired to construct the beamline with safety and compact. It is necessary for the purpose to verify the detailed evaluation technique. Therefore, taking the SPEAR3 bending magnet and BL11-3 wiggler beamlines in the examples, the characteristics of the codes were investigated in comparison with synchrotron radiation shielding design code PHOTON, STAC8 and Monte Carlo simulation code EGS4, FLUKA
