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Okumura, Keisuke; Sakamoto, Yukio*; Tsukiyama, Toshihisa*
Shahei Kaiseki No V&V Gaidorain Sakutei Ni Mukete, p.4 - 8, 2023/03
no abstracts in English
Iwamoto, Hiroki; Meigo, Shinichiro; Nakano, Keita; Yee-Rendon, B.; Katano, Ryota; Sugawara, Takanori; Nishihara, Kenji; Sasa, Toshinobu; Maekawa, Fujio
JAEA-Research 2021-012, 58 Pages, 2022/01
JAEA-Research-2021-012.pdf:7.23MB
A radiation shielding analysis was performed for the structure located above the spallation target of an accelerator-driven system (ADS), assuming one cycle of an 800 MW thermal and 30 MW beam power operation. In this analysis, the Monte Carlo particle transport code PHITS and the activation analysis code DCHAIN-PHITS were used. The structures to be analyzed are a beam duct above the target, a beam transport room located above the ADS reactor vessel, beam transport equipment, and the room ceiling. For each structure, the radiation doses and radioactivities during and after the operation were estimated. Furthermore, the shielding structure of the ceiling was determined. As a result, it was found that the radiation dose at the site boundary would be sufficiently lower than the legal limit by applying the determined shielding structure. Moreover, under the condition of this study, it was shown that the effective dose rate around the beam transport equipment positioned above the target after the operation exceeded 10 mSv/h, and that the maintenance and replacement of the equipment in the room would require remote handling.
-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
Sato, Satoshi; Iida, Hiromasa; Yamauchi, Michinori*; Nishitani, Takeo
Radiation Protection Dosimetry, 116(1-4), p.28 - 31, 2005/12
Times Cited Count：3 Percentile：23.64(Environmental Sciences)no abstracts in English
; Takemura, Morio*
JNC TJ9440 2000-005, 157 Pages, 2000/03
With use of the two-dimensional discrete ordinates code DORT and the standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the representative configurations in the Radial Shield Attenuation Experiment of the JASPER were performed. The results were compared with those obtained with use of traditional method DOT3.5/JSDJ2 for the previous JASPER experimetal analyses. In general, the change of the cross section library gives higher results and the change of the transport code gives lower results. Finally the new analysis method gives better agreement with the experimental results and also less deviations of calculational errors between various detectors. Experimental analyses for the thick concrete configulation in the Gap Streaming Experiment of the JASPER was also performed with the new analysis method, after solving the poor agreement found in last year with the original JASPER experimental analyses. The same tendency due to the library change was confirmed with the above mentioned analyses of the Radial Shield Attenuation Experiment. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments were continued through the above-mentioned experimental analyses and related informations were added for repletion of the database preserved in a computer disk holding previously accumulated data. Input data descriptions were made for auxiliary routines needed for the experimental analyses and their sample data were compiled and stored in the database.
Sato, Satoshi
Journal of Nuclear Science and Technology, 37(Suppl.1), p.253 - 257, 2000/03
no abstracts in English
Sato, Satoshi; Iida, Hiromasa
Journal of Nuclear Science and Technology, 37(Suppl.1), p.258 - 262, 2000/03
no abstracts in English
Sato, Satoshi; Iida, Hiromasa; R.Pleuteda*; Santoro, R. T.*
Fusion Engineering and Design, 46(1), p.1 - 9, 1999/00
Times Cited Count：6 Percentile：44.94(Nuclear Science & Technology)no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Seki, Yasushi; ; ; Iida, Hiromasa; Plenteda, R.*; Santoro, R. T.*; Valenza, D.*; Ohara, Yoshihiro; et al.
Fusion Technology, 34(3), p.1002 - 1007, 1998/11
no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; ; Iida, Hiromasa; Mori, Seiji*; R.Santoro*
Fusion Engineering and Design, 42, p.213 - 219, 1998/00
Times Cited Count：1 Percentile：14.76(Nuclear Science & Technology)no abstracts in English
Takemura, Morio*
PNC TJ9055 97-001, 112 Pages, 1997/03
With use of a standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the Axial Shield Experiment (homogeneous and central blockage type shield configurations with B
C or stainless steel shield material) were performed. The results were compared with those obtained by the same analysis method and input data using JSDJ2 library that had been applied consistently to the JASPER experiment analyses. In general, the results with JSSTDL analyses are higher than those by JSDJ2 as were found in analyses in last year for the Radial Shield Attenuation Experiment and the Special Materials Experiment. Consideration was made on the discrepancies between JSSTDL and JSDJ2 analysis results of the Axial Shield Experiment and also those of the sodium configulation in the Radial Shield Attenuation Experiment. The former was done by exchange of macro cross section of each region, and the latter forcused on sodium cross section was done with use of cross section sensitivity analysis method. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments, that were selected in previous study in last year, were continued and new data were added into the computer disk holding previous ones.
Sato, Satoshi; Takatsu, Hideyuki; ; ; Iida, Hiromasa; R.Santoro*
Fusion Technology 1996, 0, p.1587 - 1590, 1997/00
no abstracts in English
Masukawa, Fumihiro; ; Naito, Yoshitaka; ; ; ;
JAERI-M 93-210, 40 Pages, 1993/11
no abstracts in English
; ; ; ; Masukawa, Fumihiro; Naito, Yoshitaka
Proc. of the Joint Int. Conf. on Mathematical Methods and Supercomputing in Nuclear Applications,Vol. 2, p.374 - 383, 1993/00
no abstracts in English
Hirao, Yoshihiro*; Matsuda, Norihiro; Sakamoto, Hiroki*; Kawano, Hidenori*; Onishi, Seiki*; Nobuhara, Fumiyoshi*
no journal, ,
no abstracts in English
Nobuhara, Fumiyoshi*; Hirao, Yoshihiro*; Matsuda, Norihiro; Sakamoto, Hiroki*; Sakamoto, Yukio*; Iwashita, Mitsushige*; Yoshioka, Kentaro*
no journal, ,
no abstracts in English
Okada, Toyofumi; Horii, Yuta; Tsubota, Yoichi; Komeno, Akira; Kikuno, Hiroshi
no journal, ,
In this research, purpose is getting gamma dose rate from MOX and PuO
containing Americium and evaluating exposure dose by calculation code. One of reasons of difference between measurement value and calculation value is scattering ray from inside of globe box panel because MOX is handled inside of globe box. Therefore, we improve measuring method (changing MOX position, applying shadow shield method) and get new data which difference between measurement value and calculation value (using ANISN) is smaller than before. Furthermore, we confirm that it can be available to apply PHITS for evaluating exposure dose.
Nobuhara, Fumiyoshi*; Hirao, Yoshihiro*; Matsuda, Norihiro; Onishi, Seiki*
no journal, ,
The Working Group for Review of Simplified Shielding Analysis Codes (WG) was established in the Radiation Science and Technology subcommittee of the Atomic Energy Society of Japan (AESJ) to identify and review issues related to existing simplified shielding analysis codes that are widely used such as actual shielding design and safety assessment. In the second phase of the WG activity, we mainly studied the point kernel code and the albedo method for the maze, and the results were summarized in the second phase report. The obtained issues related to the point kernel code will be reflected in the research program started in 2020 adopted in the Radiation Safety Research Program.
