Title :
Hefei tokamak Experimental Hybrid Reactor conceptual design
Author :
Qiu, L.J. ; Luan, G.S. ; Xu, Q. ; Guo, Z.J. ; Gao, X.H. ; Duan, P. ; Zhang, X.Q. ; Li, Y.Y. ; Xu, W.N. ; Wu, Y. ; Wu, W.Y. ; Xia, C.G. ; Huang, Q.Y. ; Chen, Y.P. ; Xiang, N. ; Yina, W. G Zhang ; Wu, Y.C. ; Chen, Y. ; Qian, C.
Author_Institution :
Inst. of Plasma Phys., Acad. Sinica, Anhui, China
fDate :
30 Sep-3 Oct 1991
Abstract :
The authors present a new concept of a hybrid reactor: using a Joint-European-Torus-like device which works in the sub-breakeven condition as a source of high-energy neutrons makes it possible to induce a blanket fission of depleted-uranium, solid breeding material, and helium cooling so that one can produce 100 kg of nuclear fuel (239Pu) per year. High temperature will be maintained by external ICRF and ECRF heating. A steady-state plasma current will be driven by LHCD. The plasma density will be maintained by pellet injection ICRF can produce a high-energy tail in the ion distribution function and lead to significant enhancement of D-T reaction rate by 2-5 times so that one can obtain a neutron source strength of 1×1019 n/s, enough for the requirement of the hybrid reactor
Keywords :
Tokamak devices; fusion reactor theory and design; hybrid reactors; Experimental Hybrid Reactor; blanket fission; high-energy neutrons; ion distribution function; pellet injection; solid breeding material; steady-state plasma current; Cooling; Helium; Inductors; Joining materials; Neutrons; Nuclear fuels; Plasma density; Plasma temperature; Solids; Tokamaks;
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
DOI :
10.1109/FUSION.1991.218764
