Results 51 to 60 of about 79,921 (199)

Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket

Yuanzineng kexue jishu, 2022
Chinese Fusion Engineering Test Reactor (CFETR) has been proposed to bridge the technology gap between the International Thermonuclear Experimental Reactor (ITER) and the Fusion Demonstration Reactor (DEMO). As the most crucial nuclear component, fusion
DAI Tao;CAO Liangzhi;HE Qingming;WU Hongchun
doaj  

A New Reliability Allocation Method Based on PSA and AHP for Fusion Reactors

Energies, 2022
Reasonable and feasible reliability index allocation is significant for improving safety and reducing costs for fusion reactors. Although the reliability index is allocated when designing some key systems, reliability allocation is not implemented from ...
Ming Sun, Taosheng Li, Jie Yu, Daochuan Ge, Ying Bai, Longlong Tao   +5 more
doaj   +1 more source

Research progress and trend of advanced tungsten composite modification used for plasma facing materials

Fenmo yejin jishu, 2023
Fusion energy is one of the effective ways to solve the energy crisis in the future, but the plasma-facing materials (PFMs) face the serious radiation and thermal shock damage from the plasma in the fusion reactor.
LUO Laima, YAN Shuo, LIU Zhen, ZAN Xiang, WU Yucheng   +4 more
doaj   +1 more source

Converting energy from fusion into useful forms

, 2013
If fusion power reactors are to be feasible, it will still be necessary to convert the energy of the nuclear reaction into usable form. The heat produced will be removed from the reactor core by a primary coolant, which might be water, helium, molten ...
Harrington, C., Jenkins, I., Kiely, C., Kovari, M.   +3 more
core   +1 more source

Study on the radiological effect of the tritium gas released from fussion reactor

He jishu
BackgroundThe amount of gaseous tritium stored and released in fusion reactor is higher than that in current fission reactors, so that tritium is an important source of potential radioactivity in fusion reactor.PurposeThis study aims to investigate the ...
ZUO Qingning, HUANG Jingyun, ZHANG Junnan, WANG Xiaoliang, BAI Xiaoping, WEI Qiming   +5 more
doaj   +1 more source

IFE Plant Technology Overview and contribution to HiPER proposal

, 2011
HiPER is the European Project for Laser Fusion that has been able to join 26 institutions and signed under formal government agreement by 6 countries inside the ESFRI Program of the European Union (EU). The project is already extended by EU for two years
Alvarez Ruiz, Jesus, Cereceda, D., Courtin, Sergio, Cuesta Lopez, Santiago, Fernández, J., Fraile García, Alberto, Garoz Gómez, David, Gonzalez Arrabal, Raquel, Gordillo, N., Guerrero, Carlo, Juarez Mañas, Rafael, Moral Fernández, Nuria, Ognissanto, Flora, Perlado Martín, José Manuel, Rio Redondo, Emma del, Rivera de Mena, Antonio, Sanz, J., Suarez, R., Sánchez, C., Victoria, M.   +19 more
core   +1 more source

Researches on reactor core in Heavy ion inertial fusion [PDF]

, 2016
In Heavy ion inertial fusion (HIF), the issues include the generation and transport of heavy ion beam (HIB), the optimum pellet structure, the realistic nuclear fusion reactor design, etc.
Iinuma, T., Karino, T., Kato, H., Kawata, S., Kondo, S., Kubo, T., Ogoyski, A. I.   +6 more
core   +1 more source

On the extrapolation to ITER of discharges in present tokamaks [PDF]

, 2007
An expression for the extrapolated fusion gain G = Pfusion /5 Pheat (Pfusion being the total fusion power and Pheat the total heating power) of ITER in terms of the confinement improvement factor (H) and the normalised beta (betaN) is derived in this ...
, A.C.C. Sips, A.G. Peeters, C. Angioni, Cordey J.G., Greenwald M., JET team (presented by Cordey J.G.), Kamada Y., Litaudon X., Luce T.C., McDonald D.C., Peeters A.G., Peeters A.G., Petty C.C., Petty C.C., Shimada M., Sips A.C.C., Wolf R.C.   +17 more
core   +2 more sources

Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management

Science and Technology of Nuclear Installations, 2022
Fusion reactors are expected to be safer, more environmentally friendly, and to have a lower nuclear proliferation risk, compared with other nuclear energy systems.
Dingqing Guo, Jinkai Wang, Chao Chen, Dongqin Xia, Nuo Yong, Daochuan Ge   +5 more
doaj   +1 more source

Diagnostic systems in DEMO: engineering design issues

, 2014
The diagnostic systems of DEMO that are mounted on or near the torus, whether intended for the monitoring and control functions of the engineering aspects or the physics behaviour of the machine, will have to be designed to suit the hostile nuclear ...
Todd, T N
core   +1 more source