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Journal Articles

Factors controlling the spatiotemporal variation of $$^{137}$$Cs in seabed sediment off the Fukushima coast; Implications from numerical simulations

Misumi, Kazuhiro*; Tsumune, Daisuke*; Tsubono, Takaki*; Tateda, Yutaka*; Aoyama, Michio*; Kobayashi, Takuya; Hirose, Katsumi*

Journal of Environmental Radioactivity, 136, p.218 - 228, 2014/10

https://doi.org/10.1016/j.jenvrad.2014.06.004
 Times Cited Count：24 Percentile：53.89(Environmental Sciences)

Major controls on spatiotemporal variations of $$^{137}$$Cs activity in seabed sediments derived from the Fukushima Dai-ichi Nuclear Power Plant accident during the first year after the accident were investigated by using numerical simulations. The model successfully reproduced major features of the observed spatiotemporal variations of $$^{137}$$Cs activity in sediments. The spatial pattern of $$^{137}$$Cs in sediments, which mainly reflected the history of $$^{137}$$Cs activity in the bottom water overlying the sediment and the sediment particle size distribution, became established during the first several months after the accident. Taking $$^{137}$$Cs activities in sediments in the coastal area and in the vicinity of the power plant into account, increased the simulated total inventory of $$^{137}$$Cs in sediments off the Fukushima coast to a value on the order of 10$$^{14}$$ Bq.

Journal Articles

Hydrogen absorption/desorption behavior through oxide layer of fuel claddings under accidental conditions

Sakamoto, Kan*; Shibata, Hiroki; Une, Katsumi*; Ouchi, Atsushi*; Aomi, Masaki*; Kurata, Masaki

Proceedings of 2014 Water Reactor Fuel Performance Meeting/ Top Fuel / LWR Fuel Performance Meeting (WRFPM 2014) (USB Flash Drive), 7 Pages, 2014/09

The depth profiles of hydrogen were measured at outer surface of fuel claddings corroded in high temperature steams at 1073-1473 K to examine the barrierness of surface oxide layer against the hydrogen absorption/desorption. The results indicated that the oxide layer would be no longer the barrier against the hydrogen under some conditions although it remained as the barrier against the oxidation.

Journal Articles

Heat capacity measurements on unirradiated and irradiated fuel pellets

Amaya, M.*; Une, Katsumi*; Minato, Kazuo

Journal of Nuclear Materials, 294(1-2), p.1 - 7, 2001/04

https://doi.org/10.1016/S0022-3115(01)00450-0
 Times Cited Count：12 Percentile：63.84(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal conductivities of irradiated UO$$_{2}$$ and (U,Gd)O$$_{2}$$

Minato, Kazuo; Shiratori, Tetsuo; Serizawa, Hiroyuki; Hayashi, Kimio; Une, Katsumi*; Nogita, Kazuhiro*; Hirai, Mutsumi*; Amaya, M.*

Journal of Nuclear Materials, 288(1), p.57 - 65, 2001/01

https://doi.org/10.1016/S0022-3115(00)00578-X
 Times Cited Count：23 Percentile：81.62(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Rim structure formation of isothermally irradiated UO$$_{2}$$ fuel discs

Une, Katsumi*; Nogita, Kazuhiro*; Shiratori, Tetsuo; Hayashi, Kimio

Journal of Nuclear Materials, 288(1), p.20 - 28, 2000/09

https://doi.org/10.1016/S0022-3115(00)00712-1
 Times Cited Count：20 Percentile：78.34(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effects of grain size and PCI restraint on the rim structure formation of UO$$_{2}$$ fuels

Une, Katsumi*; Nogita, Kazuhiro*; Suzaka, Yojiro*; Hayashi, Kimio; Ito, Kunio*; Eto, Yoshinori*

International Topical Meeting on Light Water Reactor Fuel Performance, 2, p.775 - 785, 2000/00

no abstracts in English

Oral presentation

Melting temperature measurement of aluminosilicate additive fuel

Matsunaga, Junji*; Une, Katsumi*; Kusagaya, Kazuyuki*; Hirosawa, Takashi; Sato, Isamu

no journal, , 

no abstracts in English

7 (Records 1-7 displayed on this page)
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