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Shikaze, Yoshiaki
Journal of Nuclear Science and Technology, 61(7), p.894 - 910, 2024/07
Times Cited Count：2 Percentile：51.90(Nuclear Science & Technology)Among the radioactive nuclides inside the nuclear reactor buildings emitted by the Fukushima Daiichi nuclear reactor accident, high-energy beta-ray sources, such as strontium-90 and yttrium-90, generate bremsstrahlung photons in the building materials, comprising the wall, floor, and interior structure. Therefore, evaluating the radiation dose of the bremsstrahlung to the workers in the nuclear reactor building is crucial for radiation protection. The precision of the evaluation calculation of the bremsstrahlung dose was investigated by comparing the Particle and Heavy Ion Transport code System (PHITS) and the GEometry ANd Tracking (GEANT4) simulation code results. In the calculation, behind various shielding plates (lead, copper, aluminum, glass, and polyethylene, with thicknesses ranging from 1.0 to 40 mm), the water cylinder was set as the evaluated material, the absorbed dose and the deposited energy spectrum by the bremsstrahlung photons were obtained, and the characteristics and differences for both simulation codes were investigated. In the comparison results of the deposited energy spectrum, the spectral shapes have consistent trends. In the energy range below several tens of keV, a peak is seen in the PHITS spectrum for the lead shielding material. In comparing the absorbed dose under various conditions of the shielding plate for generating bremsstrahlung photons, most results for both codes correlate within an 
10% difference for 2.280 MeV beta-ray sources and an 20% difference for 0.5459 MeV beta-ray sources, except for 30% for 20 mm thick lead. Although there were differences in some cases, the evaluation results of the two simulation codes were concluded to correlate well with the above precision.
Toigawa, Tomohiro; Tsubata, Yasuhiro; Kai, Takeshi; Furuta, Takuya; Kumagai, Yuta; Matsumura, Tatsuro
Solvent Extraction and Ion Exchange, 39(1), p.74 - 89, 2021/00
Times Cited Count：2 Percentile：7.71(Chemistry, Multidisciplinary)Absorbed-dose estimation is essential for evaluation of the radiation feasibility of minor-actinide-separation processes. We propose a dose-evaluation method based on radiation permeability, with comparisons of heterogeneous structures seen in the solvent-extraction process, such as emulsions forming in the mixture of the organic and aqueous phases. A demonstration of radiation-energy-transfer simulation is performed with a focus on the minor-actinide-recovery process from high-level liquid waste with the aid of the Monte Carlo radiation-transport code PHITS. The simulation results indicate that the dose absorbed by the extraction solvent from alpha ray depends upon the emulsion structure, and that from beta and gamma ray depends upon the mixer-settler-apparatus size. Non-negligible contributions of well-permeable gamma rays were indicated in terms of the plant operation of the minor-actinide-separation process.
Saito, Kimiaki; Yamamoto, Hideaki
Radioisotopes, 63(11), p.519 - 530, 2014/11
This article aims to provide the basic meanings and features of the doses frequently used in the measurements and evaluations of environmental radiation due to the Fukushima Dai-ichi Nuclear Power Plant accident. The following doses are explained and compared: absorbed dose as basic physical quantity; effective dose and equivalent dose for judgment in radiation protection; and ambient dose equivalent 
(10) and individual dose equivalent 
p(10) for radiation measurements.
Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 42(10), p.877 - 887, 2005/10
Times Cited Count：3 Percentile：23.72(Nuclear Science & Technology)Three kinds of tissue substitutes were synthesized in order to develop a physical phantom for neutron dosimetry. The optimal elemental compositions and densities were determined using a Monte Carlo simulation method, based on absorbed dose distributions of neutrons of a few MeV in various materials. The characteristics of the synthesized tissue substitutes were verified by absorbed dose measurements using monoenergetic neutron sources and a 
Cf neutron source. It was found that the developed tissue substitutes, NAN-, HAI- and HONE-JAERI, have tissue equivalence to actual tissues within 10 % accuracy for neutrons in most of common fast neutron fields.
Nakamura, Takemi*; Tonoike, Kotaro; Miyoshi, Yoshinori
Radiation Protection Dosimetry, 110(1-4), p.483 - 486, 2004/09
Times Cited Count：2 Percentile：16.89(Environmental Sciences)Dose measurement and evaluation technique in criticality accident conditions with a thermo luminescence dosimeter (TLD) was studied at the Transient Experiment Critical Facility (TRACY) of Japan Atomic Energy Research Institute (JAERI). The tissue absorbed dose can be derived from the ambient dose equivalent given by measurement with a TLD using the conversion factor given by computation. Using this technique, the neutron dose around the SILENE reactor of the Institute for Radioprotection and Nuclear Safety (IRSN) of France was measured in the Accident Dosimetry Intercomparison Exercise (June 10-21, 2002) organized by OECD/NEA and IRSN. In this exercise, the 
dose was also measured with a TLD. In this report, measurements and evaluation results at TRACY and SILENE are presented.
Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori; Oeda, Mikihiro*; Kurosawa, Naohiro*
JAERI-Data/Code 2004-010, 19 Pages, 2004/06
JAERI-Data-Code-2004-010.pdf:1.92MB
JAERI-Data-Code-2004-010-appendix(CD-ROM).zip:12.12MB
This report is a revised edition of "Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II)"(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) unit instead of Air Absorbed Dose Rate (Gy/h) unit, and the records of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer.
Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 41(Suppl.4), p.132 - 135, 2004/03
A solid material improved in hydrogen and oxygen contents was synthesized for development of a physical phantom for neutron. The elemental composition and density are aimed for those of the soft tissue in ICRU Report 44. The soft tissue equivalence has been verified by an absorbed dose measurement using a 252Cf neutron source. In the present work, absorbed doses were measured for the purpose of examinations of the characteristic of the synthesized soft tissue substitute for neutron of various energies, using mono-energetic 0.565 MeV neutrons from 
Li(p,n) reaction and 5 MeV from D(d,n) reaction, and quasi-mono-energetic ones (40 and 65 MeV) produced via Li(p,n) reaction. The measured absorbed doses were compared with those calculated by Monte Carlo simulation codes. The results indicate that the tissue substitute has a characteristic of soft tissue equivalence for neutron in the energy range from several hundred keV up to approximately 100 MeV.
Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 40(12), p.1027 - 1031, 2003/12
Times Cited Count：1 Percentile：10.63(Nuclear Science & Technology)To develop a physical phantom for neutron dosimetry, a solid soft-tissue substitute was synthesized. The hydrogen and oxygen compositions of the synthesized tissue substitute, NAN-JAERI, are similar to those of the soft tissue in ICRU Report 44. To examine the radiation characteristics of the new soft-tissue substitute, absorbed dose distributions in NAN-JAERI were measured using a Cf neutron source. The measured absorbed dose distributions of neutrons and photons agree with those calculated by a Monte Carlo simulation code MCNP. The agreement between the experiment and the simulation verifies this method of evaluating the soft-tissue equivalence of NAN-JAERI for Cf neutrons. Similar simulations for some mono-energetic neutron sources showed that the newly developed tissue substitute has soft-tissue equivalent characteristics in the neutron energy range up to 14 MeV, in terms of the absorbed dose distributions in a slab phantom.
Nakane, Yoshihiro; Sakamoto, Yukio
Proceedings of 5th Specialists' Meeting on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-5), p.241 - 252, 2000/00
no abstracts in English
Co -ray calibration laboratory for radiation processingTachibana, Hiroyuki; Kojima, Takuji; ; ; Yotsumoto, Keiichi; Tanaka, Ryuichi
Radioisotopes, 48(4), p.247 - 256, 1999/04
no abstracts in English
Co -ray dosimetry at JAERI involving a two-way dose intercomparison study with NPL in the dose range 1-50kGyKojima, Takuji; Tachibana, Hiroyuki; ; ; P.H.G.Sharpe*
Radiation Physics and Chemistry, 54(6), p.619 - 626, 1999/00
Times Cited Count：10 Percentile：60.01(Chemistry, Physical)no abstracts in English
; ; Takasaki, Koichi*; ;
JAERI-Review 98-005, 203 Pages, 1998/03
JAERI-Review-98-005.pdf:8.96MB
no abstracts in English
Saito, Kimiaki; Sakamoto, Ryuichi; Nagaoka, Toshi; Tsutsumi, Masahiro; Moriuchi, Shigeru*
Radiation Protection Dosimetry, 69(1), p.61 - 67, 1997/00
Times Cited Count：13 Percentile：69.92(Environmental Sciences)no abstracts in English
-ray dose intercomparison in the absorbed dose range, 5-50kGy, using dichromate and alanine dosimetersH.H.Mai*; Ng.D.Duong*; Kojima, Takuji
Applied Radiation and Isotopes, 47(2), p.259 - 261, 1996/00
Times Cited Count：2 Percentile：24.47(Chemistry, Inorganic & Nuclear)no abstracts in English
; Tanaka, Shunichi; Nakane, Yoshihiro; Namito, Yoshihito*; Hirayama, Hideo*; Ban, Shuichi*;
Health Physics, 68(2), p.253 - 260, 1995/02
Times Cited Count：9 Percentile：65.83(Environmental Sciences)no abstracts in English
-ray sources simulating skin contaminationYoshida, Makoto;
Hoken Butsuri, 28, p.187 - 193, 1993/00
no abstracts in English
Tanaka, Ryuichi; Sunaga, Hiromi; Kojima, Takuji
High Dose Dosimetry for Radiation Processing, p.189 - 201, 1991/00
no abstracts in English
Taki, Mitsumasa; Kobayashi, Hideo; Suzuki, Takashi; Shimizu, Isamu
JAERI-M 90-206, 345 Pages, 1990/11
no abstracts in English
Moriuchi, Shigeru; Tsutsumi, Masahiro; Saito, Kimiaki
Hoken Butsuri, 25, p.121 - 128, 1990/00
no abstracts in English
Ikezoe, Yasumasa; ; Nakajima, Hayato; ;
Journal of Nuclear Science and Technology, 23(2), p.179 - 181, 1986/00
Times Cited Count：1 Percentile：27.82(Nuclear Science & Technology)no abstracts in English
