Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Hiromasa Sugata"'
Publikováno v:
Journal of Nuclear Science and Technology. 52:1247-1252
Specimens of (U, Pu, Zr)O2 were prepared as simulated corium debris that were assumed like debris generated in the severe accident of the Fukushima Daiichi Nuclear Power Plant and their melting tem...
Autor:
Akira Komeno, Motoaki Kashimura, Masato Kato, Hiroki Uno, Kenji Konashi, Hiromasa Sugata, Nobuo Nakae
Publikováno v:
Journal of Nuclear Materials. 393:134-140
In plutonium compounds, the lattice parameter increases due to self-radiation damage by α-decay of plutonium isotopes. The lattice parameter change and its thermal recovery in plutonium and uranium mixed dioxide (MOX) were studied. The lattice param
Autor:
Tomoyuki Abe, Kyoichi Morimoto, Motoaki Kashimura, Masato Kato, Kenji Konashi, Hiromasa Sugata
Publikováno v:
Journal of Alloys and Compounds. 452:48-53
Solidus and liquidus of mixed oxides of plutonium and uranium were measured as a function of Pu-content and oxygen-to-metal ratio using the thermal arrest technique. The solidus and the liquidus were observed to decrease with increasing Pu-content an
Autor:
Kyoichi Morimoto, Motoaki Kashimura, Kenji Konashi, Tomoyuki Abe, Hiromasa Sugata, Masato Kato
Publikováno v:
Journal of Nuclear Materials. 373:237-245
The melting of plutonium and uranium mixed oxide containing Pu of more than 30% was investigated using a tungsten capsule and a rhenium inner capsule. In the conventional measurements of (Pu, U)O 2.00 in the tungsten capsule, a liquid phase of tungst
Autor:
Kyoichi Morimoto, Tomoyuki Abe, Shinya Nakamichi, Masato Kato, Kenji Konashi, Motoaki Kashimura, Hiromasa Sugata
Publikováno v:
Scopus-Elsevier
Autor:
Hiroki Uno, T. Tamura, Hiromasa Sugata, Kyoichi Morimoto, A. Hanari, Takeo Sunaoshi, S. Kono, Masato Kato
Publikováno v:
Journal of Physics and Chemistry of Solids. 66:634-638
The development of low decontaminated mixed oxide (MOX) fuel, which contains minor actinoides (MA) and fission products (FP), is in progress to established Advanced Fast Reactor (FR) Fuel Cycle system. This paper describes the study on the sintering
Autor:
Hiromasa Sugata, Tomoyuki Abe, Motoaki Kashimura, Kyoichi Morimoto, Kenji Konashi, Masato Kato
Publikováno v:
ChemInform. 39
Solidus and liquidus of mixed oxides of plutonium and uranium were measured as a function of Pu-content and oxygen-to-metal ratio using the thermal arrest technique. The solidus and the liquidus were observed to decrease with increasing Pu-content an