Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Temporal and spatial variations of radiocarbon in Japan Sea Bottom Water

Kumamoto, Yuichiro*; Aramaki, Takafumi*; Watanabe, Shuichi*; Yoneda, Minoru*; Shibata, Yasuyuki*; Togawa, Orihiko; Morita, Masatoshi*; Shitashima, Kiminori*

Journal of Oceanography, 64(3), p.429 - 441, 2008/06

 Times Cited Count:11 Percentile:25.29(Oceanography)

In 1995 and 2000, radiocarbon ratio ($$Delta$$$$^{14}$$C) of total dissolved inorganic carbon was measured in the Japan Sea, a semi-closed marginal sea in the western North Pacific, where deep and bottom waters are formed in itself. Compiling them with historical radiocarbon data in the Japan Sea, temporal and spatial variations of the radiocarbon in the bottom water below 2000 m depth were elucidated. $$Delta$$$$^{14}$$C in the bottom waters in the western Japan and Yamato Basins increased by about 20 ‰ between 1977/79 and 1995 and did not changed between 1995 and 1999/2000, suggesting penetration of surface bomb-produced radiocarbon into the bottom waters due to bottom ventilation in the earlier period and stagnation of the bottom ventilation in the following period, respectively. In the eastern Japan Basin, the bottom $$Delta$$$$^{14}$$C increased by about 10 ‰ between 1977/79 and 2002, suggesting less ventilation of the bottom water in the basin. The temporal changes of the radiocarbon, tritium, and dissolved oxygen suggest sporadic occurrences of the bottom ventilation between 1979 and 1984 and its stagnation between 1984 and 2004 in the eastern Japan and Yamato Basins. The former is probably due to spreading of a newly ventilated bottom water in the western Japan Basin in the severe winter of 1976-1977 along the abyssal circulation in the Japan Sea. The latter does not conflict with temporal changes of bomb-produced $$^{137}$$Cs and chlorofluorocarbon-11 in the bottom water.

Journal Articles

Development of a simple reprocessing process using selective precipitant for uranyl ions; Engineering studies on systems for precipitating and separating

Yamasaki, Kazuhiko*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Kikuchi, Toshiaki*; Hanzawa, Masatoshi*; Morita, Yasuji; Ikeda, Yasuhisa*

Progress in Nuclear Energy, 47(1-4), p.414 - 419, 2005/00

 Times Cited Count:3 Percentile:24.17(Nuclear Science & Technology)

The simple reprocessing method based on precipitation using N-cyclohexyl-2-pyrrolidone (NCP) as a selective precipitant for U and Pu ions from dissolved solutions of spent FBR fuels has been developed. On the basis of fundamental studies on precipitation behaviors, we designed and built up the scaled-up laboratory equipments (1/20-scale of future plant capacity of 200 tHM/y) to evaluate technological and economical feasibility. This system, which mainly consists of a precipitator and a precipitate separator, should be operated continuously from economical reasons. From the experimental results, it was confirmed that the precipitator is capable of producing UO$$_{2}$$$$^{2+}$$-NCP precipitate stably with stipulated residence time (approximately 30 min), and the precipitate separator has the highly efficient separation of precipitate from the slurry. Furthermore, the parametric experiments indicated that the rinsing operation increased the efficiency in decontamination of FP elements.

Oral presentation

Development of a simple reprocessing process by selective precipitation for uranyl ions

Kikuchi, Toshiaki*; Yamasaki, Kazuhiko*; Kusama, Makoto*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Hanzawa, Masatoshi*; Koshino, Nobuyoshi*; Asanuma, Noriko*; Harada, Masayuki*; Kawata, Yoshihisa*; et al.

no journal, , 

no abstracts in English

Oral presentation

Pulse neutron imaging experiments in the first year of J-PARC

Kai, Tetsuya; Harada, Masahide; Oikawa, Kenichi; Sakai, Kenji; Maekawa, Fujio; Oi, Motoki; Shinohara, Takenao; Aizawa, Kazuya; Takata, Shinichi; Arai, Masatoshi; et al.

no journal, , 

Development of imaging techniques with pulse neutrons were started using the NeutrOn Beam-line for Observation and Research Use (NOBORU) of J-PARC at December 2008. The results in the first three months, future research plans and discussions on a new imaging facility in J-PARC are shown.

Oral presentation

Development of a passive safety shutdown device to prevent core damage accidents in fast reactors, 5; The Device structure concept and basic evaluations of fuel migration behavior in the device by visualization experiments

Sekio, Yoshihiro; Sato, Isamu*; Kawashima, Masatoshi*; Morita, Koji*

no journal, , 

A proposed passive reactor shutdown device contains pins with fuels that are kept in the solid state during normal operation but melt into the liquid when its temperature exceeds a prescribed value under severe accidents. The device leads reactor to subcritical state by liquid fuel migration to low positions in the pins. In this study, the device structure for fast reactor core was proposed based on safety evaluation results. The liquid fuel is needed to migrate before the accident occurs, and the migration time would depend on the fuel viscosity. To obtain basic acknowledge for determination of fuel chemical components, the effect of material viscosities on fuel migration time was evaluated through visualization experiments using liquid samples with different viscosities.

Oral presentation

Development of a passive safety shutdown device to prevent core damage accidents in fast reactors, 9; Basic evaluations of fuel migration behavior in the device by visualization experiments

Sekio, Yoshihiro; Sato, Isamu*; Kawashima, Masatoshi*; Morita, Koji*

no journal, , 

A proposed passive reactor shutdown device contains pins with fuels that are kept in the solid state during normal operation but melt into the liquid when its temperature exceeds a prescribed value under severe accidents. The device leads reactor to subcritical state by liquid fuel migration to low positions in the pins. In this study, for the purpose of obtaining basic knowledge for evaluating the engineering feasibility of the proposed device structure, we made a simulated device pin using a simulated solid fuel, a thin pipe and so on. The melting and migrating behaviors of the solid fuel in the pin were evaluated through visualization experiments.

7 (Records 1-7 displayed on this page)
  • 1