Zobrazeno 1 - 10
of 52
pro vyhledávání: '"Fumihisa Nagase"'
Publikováno v:
Nuclear Technology. 208:484-493
A control rod alloy composed of silver (Ag), indium (In), and cadmium (Cd) was heated in argon or oxygen at 1073 to 1673 K for 60 to 3600 s. Then, the release behaviors of the elements were analyze...
Autor:
Fumihisa Nagase
Publikováno v:
Annals of Nuclear Energy. 171:109052
Publikováno v:
Corrosion Reviews. 35:129-140
Light-water reactor (LWR) fuel cladding shall retain the performance as the barrier for nuclear fuel materials and fission products in high-pressure and high-temperature coolant under irradiation conditions for long periods. The cladding also has to
Publikováno v:
Nuclear Technology. 196:499-510
The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) project, run by the Organisation for Economic Co-operation and Development/Nuclear Energy Agency, was estab...
Autor:
Shinichiro Yamashita, Shuhei Miwa, Masahiko Osaka, Fumihisa Nagase, Masaki Amaya, Kosuke Tanaka, Akihiro Ishimi
Publikováno v:
Energy Procedia. 71:168-181
We have launched a new research program for evaluation of fission product and actinide release behaviour under severe accident conditions, focusing on their chemical forms. In this research program, the fission product and actinide release models inc
Publikováno v:
Journal of Nuclear Science and Technology. 51:968-976
The jet breakup phenomena of the molten cores during a severe accident are affected by some complicated structures, such as control rod guide tubes, instrument guide tubes, and core support plate, ...
Publikováno v:
Journal of Nuclear Science and Technology. 51:1125-1132
To evaluate fracture resistance of light water reactor fuel rods under loss-of-coolant accident (LOCA) and post-LOCA cooling conditions, four-point-bend tests were performed on non-irradiated Zirca...
Publikováno v:
Journal of Nuclear Materials. 445:78-83
Breakaway oxidation, which is characterized by sudden increases in oxidation rate and significant hydrogen absorption after longer exposure in high-temperature steam, was examined for the ballooned and ruptured cladding. Short test rods with PWR-type
Autor:
Fumihisa Nagase
Publikováno v:
Journal of the Atomic Energy Society of Japan. 56:235-239