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JAEA Reports

Improvement of the resuspension model for OSCAAR using the atmosphere-soil-vegetation model SOLVEG-R (Contract research)

Nakanishi, Chika*; Ota, Masakazu; Hirouchi, Jun; Takahara, Shogo

JAEA-Research 2023-012, 29 Pages, 2024/02

JAEA-Research-2023-012.pdf:6.05MB

The OSCAAR program is a probabilistic risk assessment program for reactor accidents developed by Japan Atomic Energy Agency. To improve the model included in the OSCAAR program, which is about long-term exposure caused by the resuspension of radioactive materials deposited on soil surfaces, we calculated resuspension factors for Cs-137. The one- dimensional atmosphere-SOiL-VEGetation model, SOLVEG-R was utilized to compute resuspension factor. The wind velocity was kept constant in this study since it significantly affects particle resuspension behavior. Our calculations indicate that wind velocities below 6 m s$$^{-1}$$ resulted in little variation in the annual mean resuspension factor at a height of 1 m. However, as wind velocities increased above 6 m s$$^{-1}$$, the resuspension factor significantly increased. The resuspension factors ranged from 10$$^{-9}$$ to 10$$^{-7}$$ m$$^{-1}$$ for wind velocities ranging from 1 m s$$^{-1}$$ to 7 m s$$^{-1}$$.

Journal Articles

Soil dust and bioaerosols as potential sources for resuspended $$^{137}$$Cs occurring near the Fukushima Dai-ichi Nuclear Power Plant

Ota, Masakazu; Takahara, Shogo; Yoshimura, Kazuya; Nagakubo, Azusa; Hirouchi, Jun; Hayashi, Naho; Abe, Tomohisa; Funaki, Hironori; Nagai, Haruyasu

Journal of Environmental Radioactivity, 264, p.107198_1 - 107198_15, 2023/08

 Times Cited Count:0 Percentile:0(Environmental Sciences)

One of the current major radiation exposure pathways from the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident-fallout is inhalation of the re-suspended $$^{137}$$Cs occurring in air. While wind-induced soil particle resuspension has been recognized as a primary mechanism of $$^{137}$$Cs resuspension, studies following the FDNPP accident suggested that fungal spores can be a significant source of the atmospheric $$^{137}$$Cs particularly in the rural areas such as difficult-to-return zone (DRZ). To elucidate the relative importance of the two resuspension phenomena, we propose a model simulating resuspension of $$^{137}$$Cs as soil particles and fungal spores, and applied it to DRZ. Our model's calculation showed that soil particle resuspension was responsible for the surface-air $$^{137}$$Cs observed during winter-spring, but could not account for the higher $$^{137}$$Cs concentrations observed in summer-autumn. The higher concentrations in the summer-autumn were in general reproduced by implementing fungal spore $$^{137}$$Cs emission, that replenished low soil particle $$^{137}$$Cs resuspension in that period. According to our model's concept, $$^{137}$$Cs accumulation in fungal spores and high spore emission rate characterized by the rural environment were likely responsible for the abundance of spore $$^{137}$$Cs in the air. It was inferred that the influence of the fungal spores on the atmospheric $$^{137}$$Cs would last longer since un-decontaminated forests still exist in DRZ.

Journal Articles

Uncertainty and sensitivity analyses for the reduction factor of sheltering for radiation exposures

Hirouchi, Jun; Takahara, Shogo; Komagamine, Hiroshi*

Journal of Radiological Protection, 42(4), p.041503_1 - 041503_12, 2022/12

 Times Cited Count:1 Percentile:29.26(Environmental Sciences)

Sheltering is one of the countermeasures against radiation exposure during nuclear accidents. The effectiveness of sheltering for inhalation exposure is often expressed by the reduction factor, which is defined as the ratio of the indoor to the outdoor cumulative radioactivity concentrations or doses. The indoor concentration is mainly controlled by the air exchange rate, penetration factor, and indoor deposition rate. Meanwhile, the air exchange rate depends on surrounding environmental conditions: the wind speed, leakage area normalized by the floor area of the house, and gross building coverage ratio. In this study, the ranges of the uncertainty of the reduction factors for particles and I$$_{2}$$ were investigated under various environmental conditions, and sensitivity analyses were conducted to understand the parameter with the most influence on the uncertainty of the reduction factor. From the results of the uncertainty analyses, the calculated reduction factor was highly variable depending on the environmental condition and the airtightness of the houses. The uncertainty ranges of the reduction factor for particles and I$$_{2}$$ were up to 0.9 and 0.3, respectively, and were smaller for newer houses. From the results of the sensitivity analyses, the wind speed was the most influential parameter on the reduction factor. Additionally, the wind speed was less influential for the reduction factor in newer houses.

Journal Articles

Penetration factor and indoor deposition rate of elementary and particulate iodine in a Japanese house for assessing the effectiveness of sheltering for radiation exposures

Hirouchi, Jun; Takahara, Shogo; Komagamine, Hiroshi*; Kato, Nobuyuki*; Matsui, Yasuto*; Yoneda, Minoru*

Journal of Radiological Protection, 41(3), p.S139 - S149, 2021/09

 Times Cited Count:2 Percentile:30.55(Environmental Sciences)

Sheltering is one of the countermeasures for protection against radiation exposures in nuclear accidents. The effectiveness of sheltering is often expressed by the reduction factor, that is the ratio of the indoor to the outdoor cumulative radioactivity concentrations or doses. The indoor concentration is mainly controlled by the air exchange rate, penetration factor, and indoor deposition rate. The penetration factor and indoor deposition rate depend on the surface and opening materials. We investigated experimentally these parameters of I$$_{2}$$ and particles. The experiment was performed in two apartment houses, three single-family houses, and chambers. The obtained penetration factor ranged 0.3 $$sim$$ 1 for particles of 0.3 $$sim$$ 1 $$mu$$m and 0.15 $$sim$$ 0.7 for I$$_{2}$$ depending on the air exchange rate. The indoor deposition rate for a house room ranged 0.007 $$sim$$ 0.2 h$$^{-1}$$ for particles of 0.3$$sim$$1 $$mu$$m and 0.2$$sim$$1.5 h$$^{-1}$$ for I$$_{2}$$ depending on floor materials.

Journal Articles

Indoor and outdoor radionuclide distribution in houses after the Fukushima Dai-ichi Nuclear Power Plant accident

Hirouchi, Jun; Takahara, Shogo; Yoshimura, Kazuya

Journal of Environmental Radioactivity, 232, p.106572_1 - 106572_6, 2021/06

AA2020-0442.pdf:0.52MB

 Times Cited Count:1 Percentile:5.8(Environmental Sciences)

Information on the radioactivity distribution inside and outside houses is useful for indoor external dose assessments. In this study, we collected both soil samples around the target houses and house material samples (i.e., of the floor, inner wall, ceiling, outer wall, and roof). The radioactivity of the samples was measured using a high-purity germanium detector. The surface contamination densities of the floor, inner wall, ceiling, outer wall, and roof relative to the ground were 3 $$times$$ 10$$^{-3}$$$$sim$$7 $$times$$ 10$$^{-2}$$, 6 $$times$$ 10$$^{-5}$$$$sim$$4 $$times$$ 10$$^{-4}$$, 7 $$times$$ 10$$^{-5}$$$$sim$$3 $$times$$ 10$$^{-4}$$, 2 $$times$$ 10$$^{-3}$$$$sim$$1 $$times$$ 10$$^{-2}$$, and 4 $$times$$ 10$$^{-3}$$$$sim$$2 $$times$$ 10$$^{-1}$$, respectively. The relative surface contamination densities varied depending on the material, its location, and the orientation of the surface.

JAEA Reports

Internal dose coefficients for various gastrointestinal absorption fractions (Contract research)

Hirouchi, Jun; Tokashiki, Yuji*; Takahara, Shogo; Manabe, Kentaro

JAEA-Research 2021-001, 284 Pages, 2021/03

JAEA-Research-2021-001.pdf:4.23MB

Doses to the public are calculated with internal dose coefficients based on the publications of the International Commission on Radiological Protection (ICRP) in OSCAAR, which is a level 3 Probabilistic Risk Assessment code developed by Japan Atomic Energy Agency (JAEA). The gastrointestinal absorption fraction, $$f_{1}$$, which is one of parameters of internal dose coefficient, is given the recommended value. However, although it has been reported that $$f_{1}$$ has uncertainty, the uncertainty analysis of $$f_{1}$$ has been performed on few radionuclides. In this report, to evaluate the influence of uncertainty of $$f_{1}$$ on the internal dose, we calculated the internal dose coefficient with various $$f_{1}$$, and derive the relationship between the coefficient and $$f_{1}$$. As a result, we indicate that the relationships are expressed by a linear function for radionuclides with a half-life of more than 0.5 days and are expressed by a cubic function for radionuclides with a half-life of less than 0.5 days.

Journal Articles

Investigation on the influence of additional protective measures on sheltering effectiveness for internal exposure

Hirouchi, Jun; Takahara, Shogo; Komagamine, Hiroshi*; Munakata, Masahiro

Proceedings of Asian Symposium on Risk Assessment and Management 2019 (ASRAM 2019) (USB Flash Drive), 7 Pages, 2019/09

no abstracts in English

Journal Articles

Investigation of reduction factor of internal exposure for sheltering in Japan

Hirouchi, Jun; Takahara, Shogo; Komagamine, Hiroshi*; Munakata, Masahiro

Proceedings of Asian Symposium on Risk Assessment and Management 2018 (ASRAM 2018) (USB Flash Drive), 8 Pages, 2018/10

no abstracts in English

Journal Articles

Dose-reduction effects of vehicles against gamma radiation in the case of a nuclear accident

Takahara, Shogo; Watanabe, Masatoshi*; Hirouchi, Jun; Iijima, Masashi*; Munakata, Masahiro

Health Physics, 114(1), p.64 - 72, 2018/01

AA2017-0033.pdf:0.55MB

 Times Cited Count:2 Percentile:20.74(Environmental Sciences)

Journal Articles

Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex, 2; Neutron scattering instruments

Nakajima, Kenji; Kawakita, Yukinobu; Ito, Shinichi*; Abe, Jun*; Aizawa, Kazuya; Aoki, Hiroyuki; Endo, Hitoshi*; Fujita, Masaki*; Funakoshi, Kenichi*; Gong, W.*; et al.

Quantum Beam Science (Internet), 1(3), p.9_1 - 9_59, 2017/12

The neutron instruments suite, installed at the spallation neutron source of the Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex (J-PARC), is reviewed. MLF has 23 neutron beam ports and 21 instruments are in operation for user programs or are under commissioning. A unique and challenging instrumental suite in MLF has been realized via combination of a high-performance neutron source, optimized for neutron scattering, and unique instruments using cutting-edge technologies. All instruments are/will serve in world-leading investigations in a broad range of fields, from fundamental physics to industrial applications. In this review, overviews, characteristic features, and typical applications of the individual instruments are mentioned.

Journal Articles

Factors affecting the effectiveness of sheltering in reducing internal exposure

Hirouchi, Jun; Takahara, Shogo; Komagamine, Hiroshi*; Watanabe, Masatoshi*; Munakata, Masahiro

Proceedings of Asian Symposium on Risk Assessment and Management 2017 (ASRAM 2017) (USB Flash Drive), 11 Pages, 2017/11

no abstracts in English

Journal Articles

Identification of penetration path and deposition distribution of radionuclides in houses by experiments and numerical model

Hirouchi, Jun; Takahara, Shogo; Iijima, Masashi; Watanabe, Masatoshi; Munakata, Masahiro

Radiation Physics and Chemistry, 140, p.127 - 131, 2017/11

BB2016-0282.pdf:0.39MB

 Times Cited Count:3 Percentile:28.52(Chemistry, Physical)

JAEA Reports

Survey on evacuation facilities in case of nuclear emergency in Shimane prefecture (Contract research)

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.

Journal Articles

Assessment of doses from external exposure in contaminated areas resulting from the Fukushima Daiichi Nuclear Power Plant accident

Takahara, Shogo; Kimura, Masanori; Kinase, Sakae; Ishikawa, Jun; Suyama, Kenya; Hosoyamada, Ryuji; Homma, Toshimitsu

Progress in Nuclear Science and Technology (Internet), 3, p.25 - 29, 2012/10

Dose assessment is one of the important issues to make decisions in contaminated areas resulting from the Fukushima Daiichi Nuclear Power Plant accident. The doses to inhabitants of contaminated areas should be assessed prospectively and retrospectively taking into account the impact from various exposure pathways. The external exposure from deposited radioactive materials of short-lived and long-lived is one of the most important pathways. In the present study, the radionuclide compositions have been evaluated by source term analysis taking into account 54 radionuclides. This analysis consists in evaluating the inventory and the fraction of the radionuclides that were released into the atmosphere. On the assumption that dose rate may be decreased due to the radioactive decay as well as weathering effects, we have assessed the dose for future and past at the contaminated areas. The assessed values are almost consistent with the measured ones during the first month.

Journal Articles

Anisotropy, reversibility and scale dependence of transport properties in single fracture and fractured zone; Non-sorbing tracer experiment at the Kamaishi mine

Sawada, Atsushi; Uchida, Masahiro; Shimo, Michito*; Yamamoto, H.*; Takahara, Hiroyuki*; Doe, T. W.*

SKB TR-01-24, p.151 - 164, 2002/00

None

Oral presentation

Risk-informed evaluation of off-site response planning for nuclear emergencies

Homma, Toshimitsu; Kimura, Masanori; Takahara, Shogo; Ishikawa, Jun

no journal, , 

It is recognized that good preparedness in advance of an emergency can substantially improve the emergency response to a nuclear or radiological accident. In particular, it is very important to provide technical guidance for the development of protective action strategies based upon a comprehensive analysis which takes into account the full range of postulated events. Probabilistic accident consequence assessment models can be very useful for providing a quantitative basis for discussing the effective emergency preparedness for appropriate protective action strategies such as sheltering, evacuation, and stable iodine prophylaxis. This paper presents the methodology and results of the risk-informed evaluation of off-site emergency planning using the level 3 PSA code, called OSCAAR developed at JAEA. Calculations of the off-site consequence have been made of postulated core damage accidents with source terms derived from a generic level 2 PSA of the reference plant.

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 2; Sensitivity analysis

Hirouchi, Jun; Takahara, Shogo; Watanabe, Masatoshi; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 1; Literature search on variation factors

Watanabe, Masatoshi; Takahara, Shogo; Hirouchi, Jun; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Examination on radionuclide deposition distribution in house after Fukushima Dai-ichi nuclear accident

Hirouchi, Jun; Takahara, Shogo; Iijima, Masashi; Watanabe, Masatoshi; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Evaluation of reduction effects for external exposures in vehicles evacuation after nuclear accident

Takahara, Shogo; Watanabe, Masatoshi*; Hirouchi, Jun; Iijima, Masashi*; Munakata, Masahiro

no journal, , 

no abstracts in English

32 (Records 1-20 displayed on this page)