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Preliminary Neutronics Design of Breed Blanket for Fusion-fission Hybrid Reactor

  • ZHAO Fengchao;LI Zaixin
  • Southwestern Institute of Physics, Chengdu 610041, China

Received date: 2012-06-28

  Revised date: 2012-07-04

  Online published: 2012-07-28


A preliminary neutronics design of breed blanket for fusion-fission hybrid reactor has been carried out based on the plasma parameters of International Thermonuclear Experimental Reactor (ITER) and casing structure. In the design of fast-fission breed blanket, the natural Uranium pebble bed is used as fuel and neutron multiplication and the Lithium silicate pebble bed is used as tritium breed material. By using FENDL21 nuclear database cross section library with native cross section library of MCNP nuclear database, the calculation and analysis are carried out with MCNP program. Through one-dimension calculation and analysis on different design proposals, a proper design proposal has been screened and then the three-dimension calculation and analysis have been implemented with the parameters of ITER. The calculation shows that the TBR of fusion-fission hybrid reactor is 1.13, it indicates that the design of breed blanket is able to meet self-sustaining of tritium and the calculation also indicates that the energy enlargement of fusion-fission hybrid reactor is 6.5 and Polonium breeding rate is 1.35, it means that the reactor is able to also product large quantities energy and Polonium and they could be used by light water reactor. Meanwhile, fission-breed ratio, power distribution, tritium production rate distribution, Polonium breeding distribution of blanket blocks, and blanket block 14 are also calculated and acquired.

Cite this article

ZHAO Fengchao;LI Zaixin . Preliminary Neutronics Design of Breed Blanket for Fusion-fission Hybrid Reactor[J]. Science & Technology Review, 2012 , 30(21) : 38 -44 . DOI: 10.3981/j.issn.1000-7857.2012.21.005