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Tsuji, Tomoya; Yoshitomi, Hiroshi; Kowatari, Munehiko*; Tanimura, Yoshihiko
Radiation Protection Dosimetry, 200(15), p.1416 - 1424, 2024/09
Times Cited Count:0 Percentile:0.00(Environmental Sciences)Kowatari, Munehiko*; Yoshitomi, Hiroshi; Nagamoto, Keisuke*; Nakagami, Koichi*; Moritake, Takashi*; Kunugita, Naoki*
Radiation Protection Dosimetry, 199(15-16), p.1807 - 1812, 2023/10
Times Cited Count:0 Percentile:0.00(Environmental Sciences)Kowatari, Munehiko*; Kubota, Takumi*; Yoshitomi, Hiroshi; Kunugita, Naoki*
Radiation Protection Dosimetry, 199(11), p.1239 - 1247, 2023/07
Times Cited Count:0 Percentile:0.00(Environmental Sciences)Kowatari, Munehiko*; Nagamoto, Keisuke*; Nakagami, Koichi*; Yoshitomi, Hiroshi; Moritake, Takashi*; Kunugita, Naoki*
Radiation Protection Dosimetry, 198(17), p.1303 - 1312, 2022/10
Times Cited Count:2 Percentile:34.71(Environmental Sciences)Kowatari, Munehiko; Tanimura, Yoshihiko; Kessler, P.*; Neumaier, S.*; Rttger, A.*
Radioisotopes, 70(1), p.1 - 18, 2021/01
Kowatari, Munehiko; Tanimura, Yoshihiko; Kessler, P.*; Rttger, A.*
Radiation Measurements, 138, p.106431_1 - 106431_6, 2020/11
Times Cited Count:1 Percentile:9.57(Nuclear Science & Technology)Kowatari, Munehiko; Nishino, Sho; Romallosa, K. M. D.*; Yoshitomi, Hiroshi; Tanimura, Yoshihiko; Oishi, Tetsuya
Radiation Protection Dosimetry, 189(4), p.436 - 443, 2020/05
Times Cited Count:0 Percentile:0.00(Environmental Sciences)The anisotropic emission of neutrons from a cylindrical X1 Cf source with the spherical external casing was experimentally determined. The influence of metal materials and shapes of the external casing to the anisotropy factor,
(
) was assessed by the Monte Carlo calculation, before performing the measurement. The results of the calculation result implied that light and spherical-shaped external casing decreases the anisotropic emission of neutrons from a cylindrical source and the nature of the material does not affect the anisotropic emission to a large extent. The experimental results obtained when a spherical-shaped aluminum protection case was employed also revealed that the anisotropy factor was close to 1.0 with a wide zenith angle range.
Yoshitomi, Hiroshi; Kowatari, Munehiko
Radiation Protection Dosimetry, 188(2), p.191 - 198, 2020/02
Times Cited Count:2 Percentile:19.27(Environmental Sciences)Kowatari, Munehiko; Yoshitomi, Hiroshi; Nishino, Sho; Tanimura, Yoshihiko; Oishi, Tetsuya; Kessler, P.*; Neumaier, S.*; Rttger, A.*
Radiation Protection Dosimetry, 186(4), P. 538, 2019/12
Times Cited Count:0 Percentile:0.00(Environmental Sciences)In the original version of this article an error occurred in Table 5. In section (b), the unit Sv h
has been amended to nSv h
. The corrected table appears below. The author apologises for this error.
Kowatari, Munehiko; Yoshitomi, Hiroshi; Nishino, Sho; Tanimura, Yoshihiko; Oishi, Tetsuya; Kessler, P.*; Neumaier, S.*; Rttger, A.*
Radiation Protection Dosimetry, 187(1), p.61 - 68, 2019/12
Times Cited Count:3 Percentile:18.62(Environmental Sciences)Kowatari, Munehiko; Yoshitomi, Hiroshi
Radioisotopes, 68(9), p.595 - 603, 2019/09
Yoshitomi, Hiroshi; Kowatari, Munehiko; Hagiwara, Masayuki*; Nagaguro, Seiji*; Nakamura, Hajime*
Radiation Protection Dosimetry, 184(2), p.179 - 188, 2019/08
Times Cited Count:2 Percentile:18.62(Environmental Sciences)Kowatari, Munehiko; Tanimura, Yoshihiko
JPS Conference Proceedings (Internet), 24, p.011037_1 - 011037_7, 2019/01
Tanimura, Yoshihiko; Nishino, Sho; Yoshitomi, Hiroshi; Kowatari, Munehiko; Oishi, Tetsuya
Progress in Nuclear Science and Technology (Internet), 6, p.134 - 138, 2019/01
At the severe nuclear accidents like the Fukushima Daiichi Nuclear Power Plant, various radionuclides will be dispersed into the environment and raise the dose rate. The -
measurements of
ray spectra and identifying radionuclides using the results are important for the radiological protection from both external and internal exposure. For this application a commercially available CdZnTe spectrometer (Kromek GR-1) was characterized at the calibration fields of FRS/JAEA. The angular dependence of the detection efficiency was studied and the efficiency was kept within 15 % degradation in
135 degree incident angle, which covers 85 % of all. The usable dose range was evaluated and the spectrometer could correctly measure the
ray spectra below 200
Gy/h.
Kowatari, Munehiko; Tanimura, Yoshihiko; Kessler, P.*; Neumaier, S.*; Roettger, A.*
Progress in Nuclear Science and Technology (Internet), 6, p.81 - 85, 2019/01
Kowatari, Munehiko; Yoshitomi, Hiroshi; Oishi, Tetsuya; Yoshizawa, Michio
Progress in Nuclear Science and Technology (Internet), 6, p.86 - 90, 2019/01
Kowatari, Munehiko; Zutz, H.*; Hupe, O.*
Radiation Protection Dosimetry, 178(1), p.48 - 56, 2018/01
Times Cited Count:0 Percentile:0.00(Environmental Sciences)In high energy photon reference fields the value of the air kerma rate is determined by using ionization chambers. From the charge collected inside the ionization chamber the dose can be calculated using a set of calibration and correction factors according to ISO 4037-2. A crucial parameter is the correction for the attenuation and scattering of the primary radiation due to the chamber wall. This parameter can be determined using Monte Carlo calculations. The evaluation of the factor was performed for a commercially available ionization chamber of the type Victoreen 550-3 under different build-up conditions. The results were verified by measurements in the R-F high energy photon fields according to ISO 4037-1 at the Physikalisch-Technische Bundesanstalt (PTB) and the Japan Atomic Energy Agency (JAEA).
Yoshitomi, Hiroshi; Hagiwara, Masayuki*; Kowatari, Munehiko; Nishino, Sho; Sanami, Toshiya*; Iwase, Hiroshi*
Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1188 - 1195, 2017/11
The equivalent doses to the lens of the eye and extremities for radiation workers should be assessed properly to ensure that the dose limits are not exceeded. Recently, the following two issues has pressed demand on more appropriate evaluation of the equivalent doses of the lens of the eye and extremity. One is the new occupational dose limit for the lens of the eye the ICRP recommended. The other is growing demand on handling of highly activated materials in the maintenance works of an accelerator and contaminated materials during the decommissioning works of nuclear facility, which increases the potential exposure risk to the extremities to a wider variety of radio-nuclides. Since the points to be assessed for the exposures to the lens of the eye and the extremities are apart from the trunk, the homogeneity of the radiation fields would be significantly impact on the assessment of these equivalent doses. However, there has been no sufficient and available method to identify the nonhomogeneous situations systematically in terms of the eye lens or extremity monitoring. The goal of this study is to provide the framework to identify the nonhomogeneous exposure situations. In order to fulfil this purpose, newly proposed indices to represent the homogeneity were calculated by Monte Carlo simulation incorporated with mathematical phantom, verifying the benchmark measurements. Important parameters that significantly impact on these indices were also shown from the various trials of calculations of homogeneity indices.
Nishino, Sho; Hoshi, Katsuya; Tsujimura, Norio; Kowatari, Munehiko; Yoshida, Tadayoshi
Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1258 - 1263, 2017/11
In order to investigate how neutron dosimeters respond in the continuous neutron fields in workplaces, we performed performance tests of four widely-used neutron survey meters in various simulated workplace neutron calibration fields established in two calibration facilities (FRS and ICF) in JAEA. As a result, we found that survey meters significantly over or underestimate neutron dose in the fields which have spectral components only in the energy range below 1 MeV, while those show good performance in the fields which have spectral components in the energy range above 1 MeV.
Kowatari, Munehiko; Yoshitomi, Hiroshi; Nishino, Sho; Tanimura, Yoshihiko; Oishi, Tetsuya; Yoshizawa, Michio
Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1230 - 1238, 2017/11
The Facility of Radiation Standards (FRS) of the Japan Atomic Energy Agency (JAEA) offers various kinds of radiation calibration fields for calibration and testing for over three decades. The FRS-JAEA offers reliable X-ray, -ray, beta-ray and neutron calibration fields with a vast range of variety. The quality and a set of neutron calibration fields are particularly mentioned. Neutron calibration fields with energies ranging between 0.025 eV and 19 MeV enable users to check the whole items for performance test. Two different sets of beta-ray calibration fields were established and served for regular calibration of dosimeters mainly used in nuclear industries. Resent research accomplishments on
-ray calibration fields can extend the upper limit of the energy up to 6 MeV. In addition to them, a simulated workplace neutron calibration field has been newly established for calibration of neutron dosimeters used inside the nuclear reactors.