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Kimura, Masanori; Oguri, Tomomi*; Ishikawa, Jun; Munakata, Masahiro
Journal of Nuclear Science and Technology, 58(3), p.278 - 291, 2021/03
Times Cited Count：1 Percentile：12.16(Nuclear Science & Technology)The authors developed an evaluation method for planning urgent protection strategies in a nuclear emergency by using a Level 3 Probabilistic Risk Assessment (PRA) code, OSCAAR. For a given accident scenario, the OSCAAR can calculate received doses in the early phase of a nuclear accident and the dose reduction effect of implementing urgent protective actions such as evacuation, sheltering, and iodine thyroid blocking. The authors considered the combination of these urgent protective actions within a precautionary action zone (PAZ) and an urgent protective action planning zone (UPZ) for an accident scenario and then calculated received doses after implementing these protective actions using the OSCAAR. After that, the authors performed sensitivity analysis for protective action models of the OSCAAR and then optimized the protection strategy by reducing doses to below generic criteria of the International Atomic Energy Agency (IAEA). Consequently, the effective urgent protection strategy for the accident scenario could be designed, such as precautionary evacuation within the PAZ, and the combination of evacuation after sheltering, sheltering in concrete building, or in normal housing and thyroid blocking within the UPZ. The developed evaluation method will be very useful in developing effective urgent protection strategies for an accident scenario.
Kimura, Masanori; Ishikawa, Jun; Oguri, Tomomi*; Munakata, Masahiro
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05
An integrated system between the THALES2 and the OSCAAR was developed in order to assist in preparing the input file of the OSCAAR. For the result of a state-of-the-art source term analysis with the THALES2, the authors implemented a preliminary analysis using the OSCAAR in order to evaluate the difference in setting of release fraction rates for the radionuclide groups. The effective dose was calculated for some cases by changing of release fraction rates divided into 1h (case 1), 3h (case 2), 5h (case 3), none (case 4) and arbitrary hours (case 5). After that, the ratio of the effective dose for these cases was compared. The result indicates that it was better to set short duration of release stages while the release fraction rates increased sharply. It seems that the case 5 is a better method in order to adapt to various accident scenarios. The method shows that it is useful for reducing the uncertainty in a Level 3 PRA analysis.
Takahara, Shogo; Watanabe, Masatoshi; Oguri, Tomomi; Kimura, Masanori; Hirouchi, Jun; Munakata, Masahiro; Homma, Toshimitsu
JAEA-Data/Code 2016-016, 65 Pages, 2017/02
JAEA-Data-Code-2016-016.pdf:2.32MB
We surveyed on structural and material data on 22 facilities which are listed in local disaster management plan in Matsue city. These facilities can be divided into educational facilities, communal facilities and gymnastic hall. Height and floor-area of rooms, as well as window-area were collected as the structural data. We also collected information on constructional materials, and density of those. In addition, mass-thicknesses of the constructional materials were evaluated based on our surveys, and compared to the previous studies which were made in Japan, U.S., and European countries. Consequently, it was found that there is no significant difference of mass-thickness of constructional materials between the results of our surveys and the previous studies. However, for gymnastic hall, since thin metal plates are used for roofs, we can point out that the mass-thickness of roofs are much lower than those for other concrete facilities and clay tile roofing wooden houses.
Oguri, Tomomi*; Takahara, Shogo; Kimura, Masanori; Homma, Toshimitsu
Progress in Nuclear Science and Technology (Internet), 4, p.767 - 770, 2014/04
Sheltering is one of the protective actions in a nuclear emergency. To introduce the actions with effect, preparedness is needed from a point of efficiency of reduction of radiation exposure and also capacity and location. In this study, we surveyed building materials and construction of real facilities listed in prefectural regional emergency prevention plans and then evaluated the shielding efficiency of these facilities for external exposure. As the results, we obtained knowledge of distribution of shielding factor for actual evacuation facilities by cloudshine and groundshine. Moreover, based on the sensitivity analyses, basic data was obtained that easily evaluate the shielding efficiency of facilities with different structures and materials from basic building models.
Oguri, Tomomi*; Masukawa, Fumihiro; Nakane, Yoshihiro; Nakashima, Hiroshi
JAEA-Data/Code 2011-026, 25 Pages, 2012/03
JAEA-Data-Code-2011-026.pdf:2.07MB
The simplified shielding calculation (SSCAT) system is a calculation system for radiation shielding design of high energy proton accelerator facilities, based on Moyer's and Tesch's formulae for bulk shielding and Stapleton's formula for neutron skyshine. SSCAT was originally developed for conceptual shielding design calculations of the J-PARC (Japan Proton Accelerator Research Complex) facilities, and was recently revised in order to cope with safety analysis for the licensing of the J-PARC facilities and shielding design for other proton accelerator facility. This report describes the recent status of SSCAT.
Matsuda, Norihiro; Iwamoto, Yosuke; Harada, Masahide; Teshigawara, Makoto; Meigo, Shinichiro; Maekawa, Fujio; Oguri, Tomomi*; Nakano, Hideo*; Nakao, Noriaki*; Nakane, Yoshihiro; et al.
JAEA-Technology 2008-030, 150 Pages, 2008/03
JAEA-Technology-2008-030.pdf:20.67MB
Radiation Shielding design/safety analysis required for licensing of the high intensity proton accelerator facility J-PARC (Japan Proton Accelerator Research Complex) is in progress, using various high-energy particle transport codes. Shielding benchmark problems, mainly based on experiments, on thick target neutron yield, beam dump geometry, deep penetration and radiation streaming were prepared and analyzed by the shielding design codes, in order to estimate the code's accuracy. The results of analyses show that the calculation results agree with the experiments within a factor of two on the whole.
Nakashima, Hiroshi; Nakane, Yoshihiro; Masukawa, Fumihiro; Matsuda, Norihiro; Oguri, Tomomi*; Nakano, Hideo*; Sasamoto, Nobuo*; Shibata, Tokushi*; Suzuki, Takenori*; Miura, Taichi*; et al.
Radiation Protection Dosimetry, 115(1-4), p.564 - 568, 2005/12
Times Cited Count：8 Percentile：49.16(Environmental Sciences)The High Intensity Proton Accelerator Project, named as J-PARC, is in progress, aiming at studies on the latest basic science and the advancing nuclear technology. In the project, the high-energy proton accelerator complex of the world highest intensity is under construction. In order to establish a reasonable shielding design, both simplified and detailed design methods were used in the shielding design of J-PARC. This paper reviews the present status of the radiation safety design study for J-PARC.
Oguri, Tomomi*; Nakashima, Hiroshi; Tanaka, Susumu; JAERI-University Collaboration Group for Accelerator Shielding Study
Journal of Nuclear Science and Technology, 41(Suppl.4), p.54 - 57, 2004/03
In shielding design of proton accelerator facilities, it applies simplified formulae and Monte Carlo calculation methods to calculation radiation streaming of access way and duct. A radiation streaming experiment was carried out in order to validate accuracy of intermediate energy region in labyrinth of access way connected to the 1st heavy ion room in TIARA at JAERI. In this paper, it is described comparing of measured data and calculations by MCNP-4B Monte Carlo code and simplified formulae. In Monte Carlo calculations, HILO86 constant set and LA150 was used for cross section data. The results of this experimental analysis show the accuracy of 50% errors for Monte Carlo calculations overall and a factor of 3 for simplified formulae. So applicability for these calculation methods in region of intermediate energy is validated.
Nakane, Yoshihiro; Harada, Yasunori; Sakamoto, Yukio; Oguri, Tomomi*; Yoshizawa, Michio; Takahashi, Fumiaki; Ishikura, Takeshi*; Fujimoto, Toshiaki*; Tanaka, Susumu; Sasamoto, Nobuo
JAERI-Tech 2003-011, 37 Pages, 2003/03
JAERI-Tech-2003-011.pdf:1.73MB
no abstracts in English
Nakane, Yoshihiro; Masukawa, Fumihiro; Oguri, Tomomi*; Nakashima, Hiroshi; Abe, Teruo*; Sasamoto, Nobuo
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1260 - 1263, 2002/08
no abstracts in English
Nakashima, Hiroshi; Shibata, Tokushi; Sawahata, Kei; Miyamoto, Yukihiro; Nakane, Yoshihiro; Masukawa, Fumihiro; Seki, Kazunari; Sato, Koichi; Oguri, Tomomi*; Hirayama, Hideo*; et al.
no journal, ,
Aiming at studies on the latest basic science and the advancing nuclear technology, the J-PARC (Japan Proton Accelerator Research Complex) project is in progress, and the high-energy proton accelerator complex of the world highest intensity is under construction. Because of its very high beam power and its energy as well as the large-scale accelerator complex, we have encountered some difficult radiation problems in the radiation safety design. This paper reviews the radiation safety policy and methods for the design to overcome the problems on the radiation safety and the status of the radiation safety estimation for licensing of J-PARC.
Takahara, Shogo; Kimura, Masanori; Homma, Toshimitsu; Oguri, Tomomi*
no journal, ,
Sheltering is one of protective actions which is carried out in a nuclear emergency. In order to estimate the radiation shielding effect of evacuation facilities, we have investigated building materials and structures of the facilities which are listed in regional disaster prevention plan for nuclear emergency of Shimane prefecture. we also developed the method of the estimation of radiation shielding effect on the basis of these information.
Oguri, Tomomi*; Takahara, Shogo; Kimura, Masanori; Homma, Toshimitsu
no journal, ,
The subject of this study is to estimate radiation shielding factor of evacuation facilities which is listed in regional disaster prevention plan for nuclear emergency of Shimane Prefecture. Using MCNP5 code, we have made calculation in the basis of the information collected from architect's blueprint of evacuation facilities.
