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Yoshimura, Kazuya; Fujiwara, Kenso; Nakama, Shigeo
Radiation Protection Dosimetry, 184(3-4), p.315 - 318, 2019/10
Times Cited Count：1 Percentile：10.81(Environmental Sciences)Hirouchi, Jun; Takahara, Shogo; Iijima, Masashi; Watanabe, Masatoshi; Munakata, Masahiro
Radiation Physics and Chemistry, 140, p.127 - 131, 2017/11
Times Cited Count：3 Percentile：28.52(Chemistry, Physical)Okumura, Keisuke
JAEA-Conf 2016-004, p.123 - 128, 2016/09
For the decommissioning of the Fukushima Daiichi Nuclear Power Station (1F), it is important to know the dose rate distribution in the primary containment vessel (PCV). However the distribution of radiation sources in PCV is not clear yet. There are three kinds of radiation sources in PCV. They are fuel debris, structures in PCV contaminated with Cs emitted at the 1F accident, and activated structures irradiated during normal reactor operating before the accident. In order to establish the evaluation method of the dose rate distribution in PCV, a preliminary calculation was carried out with JENDL-4.0. As a result, the sensitivity of each source to the dose distribution was obtained.
Tsuda, Shuichi; Sato, Tatsuhiko; Ogawa, Tatsuhiko
Radiation Protection Dosimetry, 168(2), p.190 - 196, 2016/02
Times Cited Count：2 Percentile：19.57(Environmental Sciences)Deposit energy distribution in microscopic site in a living cell is important information for understanding of biological effects of energetic heavy ion beams. In this work, a wall-less tissue equivalent proportional counter has been used for the measurement of lineal energy (y) distributions and dose-mean of y (yD) at radial direction of 30 MeV H at TIARA, for the verification of the microdosimetric function of PHITS. The measured yf(y) summed in radial direction agree with the corresponding data from the microdosimetric calculations using the PHITS code fairly well. The yD of 30 MeV proton beam presents the smallest value at r = 0.0 and gradually increase with radial distance, while the values of heavy ions such as iron showed rapid decrease with radial distance. This experimental result demonstrates that the stochastic deposit energy distribution of high-energy protons in microscopic region is rather constant both in the core and in the penumbra region of the track structure.
Mikami, Satoshi; Matsuda, Norihiro; Ando, Masaki; Kinase, Sakae; Kitano, Mitsuaki; Kawase, Keiichi; Matsumoto, Shinichiro; Yamamoto, Hideaki; Saito, Kimiaki
Radioisotopes, 64(9), p.589 - 607, 2015/09
This article presents the features of regional distributions and temporal changes in air dose rate and radionuclide deposition densities in Fukushima on the basis of analyses on large-scale environmental monitoring results using diverse methods. The continuity of decontamination effects is discussed according to repeated monitoring data after the decontamination model project. Further, some examples are shown on the projection of air dose rates together with the ecological half lives for different land uses.
Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 42(10), p.877 - 887, 2005/10
Times Cited Count：3 Percentile：24.17(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.
Yoshizawa, Michio; Tanimura, Yoshihiko; Saegusa, Jun; Nemoto, Hisashi*; Yoshida, Makoto
Radiation Protection Dosimetry, 110(1-4), p.81 - 84, 2004/09
Times Cited Count：3 Percentile：23.51(Environmental Sciences)The facility of Radiation Standards (FRS) of JAERI has equipped with the concrete-moderated neutron calibration fields as simulated workplace neutron fields. The fields use an Am-Be (37GBq) neutron source placed in the narrow space surrounded by concrete wall and bricks to produce scattered neutrons. The neutron spectra of the fields were measured with Bonner multi-sphere spectrometer system (BMS), spherical recoil-proton proportional counters (RPCs), and a liquid scintillation counter (NE-213). The results were compared with each other, and the neutron spectra and the ambient dose equivalent rate, 
(10), were agreed well within the uncertainty. The angular distributions of neutron fluence were calculated by the MCNP-4B2 Monte Carlo code to obtain the reference personal dose equivalent rate, 
(10). The calculated results show that the scattered neutrons have a wide variety of incident angles. The reference (10) values considered the angular distribution were found to be 10-18% smaller than those without consideration.
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.
Endo, Akira; Yamaguchi, Yasuhiro
Radiation Research, 159(4), p.535 - 542, 2003/04
Times Cited Count：14 Percentile：39.81(Biology)The first criticality accident in Japan occurred in a uranium processing plant in Tokai-mura in September, 1999. In this accident, two workers on the site were heterogeneously exposed to neutrons and 
rays produced by the nuclear fission. Heterogeneous exposure influenced the clinical course observed in the skin and organs of these workers. By request from medical groups, we attempted to clarify the dose distribution of the two heavily exposed workers with the aid of computer simulation, which is currently the only means by which to address this complicated problem. This paper presents elucidated skin dose distributions, depth dose distributions inside the trunk, and neutron-to- dose ratios.
Kumada, Hiroaki; Torii, Yoshiya
JAERI-Data/Code 2002-018, 158 Pages, 2002/09
JAERI-Data-Code-2002-018.pdf:30.28MB
A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images and that generates a input data file automaticly for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patinet's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0)
Yamamoto, Tetsuya*; Matsumura, Akira*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Shibata, Yasushi*; Nose, Tadao*
Physics in Medicine & Biology, 47(14), p.2387 - 2396, 2002/07
Times Cited Count：27 Percentile：58.02(Engineering, Biomedical)The aim of this study was to determine the in-phantom thermal distribution derived from neutron beams for intraoperative boron neutron capture therapy (IOBNCT). Gold activation wires arranged in a cylindrical water phantom with (void-in phantom) or without (standard phantom) a cylinder styrene form placed inside were irradiated by using the epithermal beam (ENB) and the mixed thermal-epithermal beam (TNB-1) at the JRR-4. The thermal neutron distribution derived from both the ENB and TNB-1 was significantly improved in the void-in-phantom, and a double high dose area was formed lateral to the void. The flattened distribution in the circumference of the void was observed with the combination of ENB and the void-in-phantom. The measurement data suggest that the ENB may provide a clinical advantage in the form of an enhanced and flattened dose delivery to the marginal tissue in which residual and/or microscopically infiltrating tumor.
Takada, Eiji*; Fujimoto, Nozomu; Nojiri, Naoki; Umeta, Masayuki; Kokusen, Shigeru; Ashikagaya, Yoshinobu
JAERI-Data/Code 2002-009, 83 Pages, 2002/05
JAERI-Data-Code-2002-009.pdf:3.51MB
Dose equivalent rate around the fuel handling machine, the control rod handling machine, stand pipe compartment, maintenance pit were measured during gamma ray measurements from HTTR fuel, which was called as “power distribution measurements". The power distribution measurement was the first time to handle the fuel blocks irradiated in the core. Dose equivalent rate measurement aiming the check of shielding performance of components, the check of unexpected streaming path. The radiation monitoring during operation was carried out. As the results, there was no problem on shielding. The measured data at operation condition were also obtained. The data will be useful to expect operation circumstance in the future.
Endo, Akira; Noguchi, Hiroshi; Tanaka, Susumu; Kanda, Yukio*; Oki, Yuichi*; Iida, Takao*; Sato, Kaoru; Tsuda, Shuichi
Applied Radiation and Isotopes, 56(4), p.615 - 620, 2002/04
Times Cited Count：3 Percentile：23.39(Chemistry, Inorganic & Nuclear)Formation mechanism and size distribution of radioactive aerosol particles generated in a high-energy neutron field were studied in order to evaluate a particle size parameter for internal dose evaluation in high-energy accelerator facilities. Argon gas containing DOP aerosols was irradiated by a 65MeV quasi-monoenergetic neutron beam of TIARA. The number size distribution of the DOP aerosols and the activity-weighted size distribution of 
Cl and 
Cl aerosols, formed from the (n, 2np) and (n, np) reactions of 
Ar, were measured using an electrical low-pressure impactor. The activity-weighted size distribution of the radioactive aerosols was well explained by the simple attachment model of the radioactive atoms to the DOP aerosols.
Kojima, Takuji; Sunaga, Hiromi; Takizawa, Haruki; Hanaya, Hiroaki; Tachibana, Hiroyuki
JAERI-Review 2001-039, TIARA Annual Report 2000, p.120 - 121, 2001/11
Gafchromic film (MD-1260) characterized for MeV/u ion beams was tested for measurement of the lateral distribution profiles in the plastic phantom. Gafchromic film was irradiated to 120 Gy using 450 MeV 
Xe
ions through the 10
thick mesh mask having 6 m line-width and 19 inner latice distance to make artificial dose distribution on the film. Analysis of radiation-induced color change of the film was tried using a microscopic spectrophotpmeter having 1 dia. analyzing light. The film has a potencial to know exact lateral irradiation area with sufficient sharpness and dose distribution by converting absorbance to dose on he basis of dose response characteristics, with spatial resolution of 1.
Hieu, N. M.*; Kumazawa, Shigeru
JAERI-Research 2000-065, 28 Pages, 2001/02
JAERI-Research-2000-065.pdf:1.63MB
no abstracts in English
Cs depth distribution in the Chernobyl groundsSakamoto, Ryuichi; Saito, Kimiaki; Tsutsumi, Masahiro; Nagaoka, Toshi; Stolyarevsky, I.*; Glebkin, S.*; Tepikin, V.*; Arkhipov, N.*; Ramzaev, V.*; Mishine, A.*; et al.
Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 5 Pages, 2000/05
no abstracts in English
;
Dekomisshoningu Giho, 0(15), p.24 - 34, 1996/12
no abstracts in English
Takehisa, Masaaki*; Saito, Toshio*; Takahashi, Toru*; *; Tanaka, Susumu; Agematsu, Takashi; *; *
Cost-benefit Aspects of Food Irradiation Processing; IAEA-SM-328/22, p.243 - 257, 1993/00
no abstracts in English
Onodera, Junichi; ; ; ; ; Ikezawa, Yoshio
Proc. of the Int. Radiation Protection Association,Vol. 1, p.1412 - 1414, 1992/00
no abstracts in English
Saito, Kimiaki
Radiation Protection Dosimetry, 35(1), p.31 - 39, 1991/00
Times Cited Count：8 Percentile：66.02(Environmental Sciences)no abstracts in English
