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Nakano, Tomohito*; Mizutani, Akira*; Abe, Sadayoshi; Tomida, Kazuo*; Handa, Hiroyuki*
Genshiryoku eye, 56(1), p.63 - 76, 2010/01
no abstracts in English
Rintsu, Yuko*; Serizawa, Shigeru*; Yamazaki, Tetsuo*; Umeyama, Nobuaki*; Moriuchi, Shigeru*; Handa, Hiroyuki*; Onishi, Ryoichi*; Takemura, Morio*; Chino, Masamichi; Nagai, Haruyasu; et al.
Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10
no abstracts in English
Masukawa, Fumihiro; Abe, Teruo*; Hayashi, Katsumi*; Handa, Hiroyuki*; Nakashima, Hiroshi
JAEA-Data/Code 2006-024, 98 Pages, 2006/11
We have developed SHINE3, simple code for high energy neutron skyshine dose evaluation, for the shielding designs of high energy accelerator facilities. This code uses the 4-parametric fitting function to the skyshine dose response by neutron and secondary -ray, which were predicted by PHITS, the general-purpose Particle and Heavy Ion Transport Monte Carlo code system. This code can be applied for skyshine dose evaluation of neutron up to 3 GeV in energy, and distance ranging between 10 and 2000 meters from source point, with equivalent accuracy as those by Monte Carlo Method.
Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03
In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.
Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*; Hirayama, Hideo*; Shin, Kazuo*
JAERI-Tech 2003-018, 42 Pages, 2003/03
no abstracts in English
Nakashima, Hiroshi; Sasamoto, Nobuo; Sakamoto, Yukio; Kusano, Joichi; Hasegawa, Kazuo; Handa, Hiroyuki*; Hayashi, Katsumi*; Yamada, Kobun*; Abe, Teruo*
Journal of Nuclear Science and Technology, 37(Suppl.1), p.870 - 874, 2000/03
no abstracts in English
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Proceedings of 1996 Radiation Protection and Shielding Division Topical Meeting, 0 Pages, 1996/00
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Shono, Akira; Tsunoda, Hirokazu; Takemura, Morio; Handa, Hiroyuki
PNC TN9410 95-171, 280 Pages, 1995/06
All experiments planned in the JASPER (Japanese-American Shielding Program for Experimental Research) project have been conducted from '85 to '92. Results obtained from the post-experimental analyses are described in the annual reports ('86'94). This report is intended to review and summarize the enormous information of the annual reports. For the evaluation, the following topics were chosen. (1)Bulk Shielding attenuation characteristics and analysis accuracy (2)Design-dependent shielding characteristics and analysis accuracy (3)Evaluation of the shielding cross section libraries (4)Improvements in shielding analysis methods. Major conclusions are briefly as follows. (a)Both bulk shielding attenuation characteristics and streaming characteristics of configurations consisting of several materials including boron-carbide(BC), graphite, stainless steel, sodium and etc. were clarified and the analysis accuracy confirmed. (b)JSDJ2 (based on the JENDL-2) was demonstrated to be a better cross section library for shielding analysis by reviewing experimental analyses results. (c)The shielding analysis system for fast reactors using a 2-dimensional discrete ordinates code as the standard has been improved and verified. (d)Useful experiences have been gained in verifying both a Monte Carlo code and a 3-dimensional discrete ordinates code, as well as in optimizing various parameters including those for mesh spacing techniques. Another objective of this report is to specify key information which will be useful to review JASPER. For this purpose, information on experiment and analysis is presented in a table format by each experimental item. All technical reports related to JASPER are listed.
Koizumi, Koichi; *; *; *; *; Takatsu, Hideyuki; Seki, Yasushi; Sato, Satoshi
JAERI-M 92-106, 62 Pages, 1992/08
no abstracts in English
Chatani, Keiji; ; ; ; *; *; *
PNC TN9410 92-076, 348 Pages, 1992/03
JASPER (Japanese American Shielding Program of Experimental Researches) is the cooperative research program between PNC and US-DOE using TSF (Tower Shielding Facility) in ORNL (Oak Ridge National Laboratory) as the experiment facility. This report summarizes the works in FY'1991 as follows; Planning the experiment configuration for JASPER Program, Analyses of the JASPER Program experiment, Analyses of the former TSF experiment, and Development of the methods for FBR shielding analyses. (1)Analyses of the JASPER Program Experiment In FY'1991 Axial shield Experiment data were mainly analyzed, and some of In-vessel Fuel Storage (IVS) Experiment data were also analyzed. The Fast Reactor Shielding Analysis System developed by PNC has been applied to the analyses for JASPER Program experiments. (Axial Shield Experiment Analysis) Axial Shield Experiment was conducted from August 1990 through December 1990 as part of a continuing series of eight experimennts planned for the JASPER Program. The experiment serves not only to provide data for the verification of analysis system in calculating the neutron streaming in each design, but also to provide a basis for determining the shielding effectiveness of stainless steel (SS) and boron carbide (BC). four types of experimental configuration were used. The conclusions of the analyses are as follows: (a)For the spectrum modifier which provides a spectrum of neutron representative of those incident on the axial shield for the FBR core, the two-dimensional calculation showed good agreement with the experimental data. It was confirmed that the two-dimensional calculation could estimate the experimental data with almost the same accuracy as in the analyses for the Radial shield Attenuation and the Fission Gas Plenum Experiments. (b)For the homogeneous mockups, the two-dimensional ealculation could give the good agreement with the experimental data. (c)For the central blockage type mockups, in which the coolant flows ...
Nakao, Noboru*; Amada, Tatsuo*; Horie, Junnosuke*; Takeuchi, Jun*; Handa, Hiroyuki*; Sebata, Masao*
PNC TJ202 84-06, 235 Pages, 1984/06
no abstracts in English
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Proceedings of 1996 Radiation Protection and Shielding Division Topical Meeting, ,
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