Zobrazeno 1 - 10
of 46
pro vyhledávání: '"Eiji HOASHI"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00494-23-00494 (2023)
In order to reduce Minor Actinides (MA), the transmutation of MA in a fast reactor has been studied in Japan. In the transmutation in the fast reactor, MAs are mixed in the ordinary MOX fuel and they are burned up. For the design of a fast reactor wi
Externí odkaz:
https://doaj.org/article/f2497071803e47298d973eddf031596f
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 87, Iss 894, Pp 20-00094-20-00094 (2021)
Electromagnetic flow meter (EMF) has been applied to measure a flow rate of sodium in circular pipe using permanent magnet for a loop-type sodium-cooled Fast Reactor (SFR), such as Monju. To extend EMF to a tank-type SFR only with an annular flow cha
Externí odkaz:
https://doaj.org/article/87fa270ba6ee433e920ed679c3e94b1a
Publikováno v:
Mechanical Engineering Journal, Vol 2, Iss 5, Pp 15-00230-15-00230 (2015)
Electromagnetic (EM) pumps, which drive liquid metals by electromagnetic force for Fast Reactor, had been developed. Annular Linear Induction Pumps (ALIPs) are one of EM pumps. There are some reports in which a drop and a fluctuation of the developed
Externí odkaz:
https://doaj.org/article/89d78071ea4c40c481b3022a4da8a8c4
Autor:
Eiji HOASHI, Sachiko YOSHIHASHI-SUZUKI, Takafumi OKITA, Takuji KANEMURA, Hiroo KONDO, Nobuo YAMAOKA, Hiroshi HORIIKE
Publikováno v:
Mechanical Engineering Journal, Vol 1, Iss 4, Pp TEP0017-TEP0017 (2014)
The international fusion materials irradiation facility (IFMIF) presents an intense neutron source to develop fusion reactor materials. The liquid metal Lithium (Li) jet with a free surface is planned as a target irradiated by two deuteron beam to ge
Externí odkaz:
https://doaj.org/article/2b7249e48fb44320ae9a85ce25dfbe8a
Publikováno v:
Journal of Nuclear Science and Technology. 59:1127-1138
Publikováno v:
Transactions of the JSME (in Japanese). 87:20-00094
Publikováno v:
Fusion Engineering and Design. 140:117-122
A tungsten divertor will be repetitively subjected to high heat fluxes when plasma disruptions or edge-localized modes occur, and the surface of the divertor will be molten and solidified repeatedly during the reactor operation. In an experiment, a t
Autor:
Takafumi Okita, Kotaro Watanabe, Eiji Hoashi, Makoto M. Nakamura, Kentaro Ochiai, Atsushi Kasugai
Publikováno v:
Fusion Engineering and Design. 179:113100
Publikováno v:
Fusion Engineering and Design. 136:350-356
Tungsten is a candidate as a surface material of divertor in Tokamak fusion reactor. A pulsed high heat flux emitted in plasma disruption and Type I Edge Localized Mode (ELM) is considered to melt the tungsten surface repeatedly. The repetitive phase
Publikováno v:
Fusion Engineering and Design. 136:178-182
Liquid Lithium is one of the candidate material of a beam target in the International Fusion Materials Irradiation Facility (IFMIF). In the IFMIF, to remove the high heat load by beam irradiation, Li is need to flow at high velocity (>15 m/s). Also,