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Publikováno v:
Nuclear Materials and Energy, Vol 29, Iss, Pp 101092-(2021)
A challenging issue for the magnetic fusion concept of generating nuclear power is the performance of plasma-facing components, particularly in the divertor within the fusion power plant. Tungsten alloys, such as W-TiC, W-La2O3, etc., are the prime c
Autor:
W. Cho, Bong Guen Hong
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss, Pp 101040-(2021)
The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability
Autor:
Delaporte-Mathurin, Rémi, Hodille, Etienne, Mougenot, Jonathan, Charles, Y., de Temmerman, Gregory, Leblond, Floriane, Grisolia, Christian
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 100984-(2021)
Nuclear Materials and Energy
Nuclear Materials and Energy, 2021, pp.100984. ⟨10.1016/j.nme.2021.100984⟩
Nuclear Materials and Energy, Elsevier, 2021, pp.100984. ⟨10.1016/j.nme.2021.100984⟩
Nuclear Materials and Energy
Nuclear Materials and Energy, 2021, pp.100984. ⟨10.1016/j.nme.2021.100984⟩
Nuclear Materials and Energy, Elsevier, 2021, pp.100984. ⟨10.1016/j.nme.2021.100984⟩
International audience; A novel identification technique of hydrogen transport parameters using FESTIM (Finite Element Simulation of Tritium In Materials) has been demonstrated. FESTIM is a finite element code developed with FEniCS performing hydroge
Autor:
Haiqing Liu, A. Higashijima, Nobuaki Yoshida, Sadayoshi Murakami, Akiyoshi Hatayama, Yasuhisa Oya, Kengoh Kuroda, Xiang Gao, T. Shikama, Yoshihiko Nagashima, S. Kawasaki, Hiroshi Idei, Yuichi Takase, Ryuya Ikezoe, Takahiro Nagata, Makoto Hasegawa, Makoto Oya, Shun Shimabukuro, Takumi Onchi, Kazuaki Hanada, Jinping Qian, Ikuji Takagi, Kazuo Nakamura
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 101013-(2021)
QUEST (Q-shu university experiment with steady state spherical tokamak) is a midsize spherical tokamak capable of steady-state operation, comprising all-metal plasma-facing walls and a hot wall (HW) to address issues pertaining to fuel particle balan
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 101001-(2021)
Nuclear Materials and Energy
Nuclear Materials and Energy
ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant to International Thermonuclear Experimental Reactor – ITER [1]. Limiters and an upper dump plate of the vacuum vessel are made
Autor:
Leon Kos, M. Brank, G. Simič, P. U. Lamalle, V. Polli, Y. Gribov, M. Kocan, R.A. Pitts, F. Köchl
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 101021-(2021)
Ion cyclotron resonance heating (ICRH) is one of the three additional heating schemes to be deployed on ITER. Its two antenna arrays, installed on the outboard midplane, will deliver 20 MW of RF power in the 40–55 MHz frequency range. The plasma-fa
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss, Pp 101005-(2021)
The duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released
Autor:
A. Nagy, D.K. Mansfield, Robert Lunsford, R. Maingi, Tamsin Osborne, G.L. Jackson, Alessandro Bortolon
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss, Pp 34-41 (2019)
Injection of low-Z granules into high performance discharges on DIII-D has been shown to promptly trigger Edge Localized Modes (ELMs) providing high-Z impurity control without significant plasma degradation. The ability to provide ELM triggering over
Autor:
R. Giniyatulin, A.V. Karpov, A. P. Sliva, A. T. Komov, A. Yu. Marchenkov, S. D. Fedorovich, D N Gerasimov, G.B. Vasiliev, A. V. Dedov, A. N. Makhankov, M. V. Lukashevsky, M K Gubkin, A. V. Zakharenkov, A. V. Lazukin, Yu. V. Martynenko, N. V. Litunovsky, V. P. Budaev
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss, Pp 100816-(2020)
Mock-ups of the ITER divertor plate are tested with the combination of steady-state plasma and e-beam loads: (1) thermocyclic tests with powerful electron beam load of up to 49 MW/m2 in the e-beam facility; and then (2) subsequent testing in the PLM
Publikováno v:
Nuclear Materials and Energy, Vol 23, Iss, Pp-(2020)
Nuclear Materials and Energy
Nuclear Materials and Energy
In a demonstrational fusion power plant (DEMO), divertor is supposed to protect vacuum vessel and superconducting magnets against neutron flux in the bottom region of the vessel. The vessel is subject to a strict design limit in irradiation damage do