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Takahashi, Fumiaki; Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 42(4), p.378 - 383, 2005/04
Times Cited Count：3 Percentile：24.22(Nuclear Science & Technology)Experiments were made to verify a dose assessment method from activated sodium in body in criticality accidents. A phantom containing sodium chloride solution was irradiated in the Transient Experiment Critical Facility to simulate activation of sodium. Monte Carlo calculations were performed to obtain quantitative relation between the activity of induced Na-24 and neutron dose in the phantom. In the previous work, conversion coefficients from specific activity of induced Na-24 to neutron dose had been analyzed with the MCNP-4B code concerning neutron spectra at some hypothesized configurations. One of the prepared coefficients was applied to evaluate neutron dose from the measured activity. The estimated dose agreed with the dose analyzed by the Monte Carlo calculation in the present study within an acceptable uncertainty, which is indicated by the IAEA. In addition, the dose calculated with the prepared coefficient was close to the result measured with dosimeters. These results suggest that the prepared coefficients can be applied to dose assessments from induced Na-24 in body.
Endo, Akira; Yamaguchi, Yasuhiro; Eckerman, K. F.*
JAERI 1347, 114 Pages, 2005/02
no abstracts in English
Endo, Akira; Yamaguchi, Yasuhiro; Eckerman, K. F.*
Radiation Protection Dosimetry, 105(1-4), p.565 - 569, 2003/09
Times Cited Count：12 Percentile：62.23(Environmental Sciences)The present paper discusses a strategy for the development of a new radioactive decay database, which will succeed ICRP Publ.38 used for dosimetry calculations. The development of the database requires 1) Consistency checking of the ENSDF used for compilation of the decay data, 2) Improvement of the computer code EDISTR for processing the ENSDF, and 3) Comparison with other decay data prepared from the different computer codes and libraries for the verification of the compiled data. This paper identifies several technical issues that need to be addressed for the development of the new radioactive decay database.
Takahashi, Fumiaki; Yamaguchi, Yasuhiro; Iwasaki, Midori*; Miyazawa, Chuzo*; Hamada, Tatsuji*; Funabiki, Jun*; Saito, Kimiaki
Radiation Protection Dosimetry, 103(2), p.125 - 130, 2003/01
Times Cited Count：4 Percentile：31.64(Environmental Sciences)Absorbed dose to tooth enamels against external photon exposure was examined by the Electron Spin Resonance (ESR) dosimetry using tooth samples placed in a realistic physical phantom. Dose to teeth region was also measured with thermo-luminescence dosimeters (TLDs). A voxel-type phantom was constructed from CT images of the physical phantom. Monte Carlo calculations with this voxel-type phantom were performed to analyse the results of the experiments. The obtained data in this study were compared to the enamel doses, which were calculated with a modified MIRD-type and already given in a previous paper. The results suggested that the conversion factors from enamel dose to organ doses obtained by the modified MIRD-type phantom are to be applicable for retrospective individual dose assessments by the ESR dosimetry. The analysis, however, indicated that the size and figure of the head can affect the enamel dose for low photon energy region below 100keV.
Kojima, Takuji; Hakoda, Teruyuki; Sunaga, Hiromi; Takizawa, Haruki; Hanaya, Hiroaki
Proceedings of 9th International Conference on Radiation Curing (RadTech Asia '03) (CD-ROM), 4 Pages, 2003/00
Dosimetry study for 300 keV electron beams was performed using Gafchromic film dosimeters having 8-
m thick radiation-sensitive layer for dose rate measurement, a prototype total-absorption aluminum calorimeter for energy fluence measurement and semi-empirical calculation using EDMULT code for depth-dose distribution estimation. The three preliminary results are compared concerning to dose rate distribution and energy fluence as a function of depth in air. Influences in dosimetry for 300 keV electrons are discussed based on these results.
Takahashi, Fumiaki; Endo, Akira; Yamaguchi, Yasuhiro
Radiation Protection Dosimetry, 106(3), p.197 - 206, 2003/00
Times Cited Count：4 Percentile：31.64(Environmental Sciences)Some data were derived using recent sophisticated methods to convert rapidly specific activity of induced sodium-24 to average dose over a whole body in criticality accidents. Monte Carlo calculations using the MCNP-4B code were performed to study energy spectra of neutrons and gamma rays for some criticality systems with fissile uranium. Absorbed dose to human body and activation of sodium were also analysed against external radiation by simulations using a phantom. It was found that neutron dose assessment from induced 
Na would be important to give an initial guidance of a treatment. The condition of neutron exposure, however, did not influence the quantitative relation dose by gamma rays induced within a body and activity of Na. Analyses were made to clarify the dependence of conversion from Na specific activity to dose on the orientation and the size of human body. This study suggested that the size of uranium solution and material around the fuel should be informed to properly estimate dose against external photons from neutron dose.
Sakamoto, Yukio
JAERI-Research 2002-025, 34 Pages, 2002/11
JAERI-Research-2002-025.pdf:1.91MB
no abstracts in English
Yokoyama, Sumi; Noguchi, Hiroshi; Ryufuku, Susumu*; Sasaki, Toshihisa*; Kurosawa, Naohiro*
JAERI-Data/Code 2002-022, 87 Pages, 2002/11
JAERI-Data-Code-2002-022.pdf:4.26MB
Tritium, which is used as a fuel of a D-T burning fusion reactor, is the most important radionuclide for the safety assessment of a nuclear fusion experimental reactor such as ITER. Thus, a computer code, ACUTRI, which calculates the radiological impact of tritium released accidentally to the atmosphere, has been developed, aiming to be of use in a discussion on licensing of a fusion experimental reactor and an environmental safety evaluation method in Japan. ACUTRI calculates an individual tritium dose based on transfer models specific to tritium in the environment. A Gaussian plume model is used for calculating the atmospheric dispersion of tritium gas (HT) and/or tritiated water (HTO). The environmental pathway model in ACUTRI considers the following internal exposures: inhalation from a primary plume (HT and/or HTO) released from the facilities and inhalation from a secondary plume (HTO) reemitted from the ground following deposition of HT and HTO. This report describes an outline of the ACUTRI code, a user guide and the results of test calculation.
-ray dose rates around the duct penetration by three-dimensional Monte Carlo decay -ray transport calculation with variance reduction methodSato, Satoshi; Iida, Hiromasa; Nishitani, Takeo
Journal of Nuclear Science and Technology, 39(11), p.1237 - 1246, 2002/11
Times Cited Count：27 Percentile：83.24(Nuclear Science & Technology)no abstracts in English
Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1433 - 1436, 2002/08
no abstracts in English
Endo, Akira; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 38(8), p.689 - 696, 2001/08
Times Cited Count：4 Percentile：33.39(Nuclear Science & Technology)no abstracts in English
Endo, Akira; Yamaguchi, Yasuhiro
JAERI-Data/Code 2001-004, 157 Pages, 2001/03
JAERI-Data-Code-2001-004.pdf:11.27MB
New nuclear decay data used for dose calculation have been compiled for 817 radionuclides that are listed in ICRP Publication 38 (Publ.38) and for 6 additional isomers. The decay data were prepared using decay data sets from the Evaluated Nuclear Structure Data File (ENSDF), the latest version in August 1997. Basic nuclear properties in the decay data sets that are important for calculating energies and intensities of emissions were updated by referring to NUBASE. In addition, possible revisions of partial and incomplete decay data sets were done for their format and syntax errors, level schemes, normalization records, and so on. After that, the decay data sets were processed by EDISTR in order to compute the energies and intensities of 
particles, 
particles, rays, internal conversion electrons, X rays, and Auger electrons. The compiled data were prepared in two different types of format: Publ.38 and NUCDECAY formats. The decay data will be widely used for dose calculations in radiation protection and will be beneficial to a future revision of ICRP Publ.38.
Endo, Akira; Yamaguchi, Yasuhiro; Sakamoto, Yukio; Yoshizawa, Michio; Tsuda, Shuichi
Radiation Protection Dosimetry, 93(3), p.207 - 214, 2001/00
Times Cited Count：6 Percentile：44.09(Environmental Sciences)no abstracts in English
Endo, Akira; Yamaguchi, Yasuhiro
Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 8 Pages, 2000/05
no abstracts in English
Endo, Akira; *; Yamaguchi, Yasuhiro
JAERI-Data/Code 99-035, 355 Pages, 1999/07
JAERI-Data-Code-99-035.pdf:14.77MB
no abstracts in English
Saito, Kimiaki; N.Petoussi*; Zankl, M.*
Health Physics, 74(6), p.698 - 706, 1998/06
Times Cited Count：47 Percentile：94.8(Environmental Sciences)no abstracts in English
Noguchi, Hiroshi; Yokoyama, Sumi
KURRI-KR-30, p.204 - 209, 1998/00
no abstracts in English
Sukegawa, Takenori; ; ; Yanagihara, Satoshi
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1779 - 1784, 1995/00
no abstracts in English
; Sakamoto, Yukio
Journal of Nuclear Science and Technology, 30(9), p.926 - 945, 1993/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
S.Zimin*; Takatsu, Hideyuki; Mori, Seiji*; *; Seki, Yasushi; Sato, Satoshi; Tada, Eisuke
JAERI-M 93-141, 75 Pages, 1993/07
no abstracts in English
