Publication Date:
2019-07-13
Description:
Fusion-fission hybrid reactors are discussed in terms of two main purposes: to breed fissile materials (Pu 233 and Th 233 from U 238 or Th 232) for use in low-reactivity breeders, and to produce tritium from lithium to refuel fusion plasma cores. Neutron flux generation is critical for both processes. Various methods for generating the flux are described, with attention to new geometries for multiple plasma focus arrays, e.g., hypocycloidal pinch and staged plasma focus devices. These methods are evaluated with reference to their applicability to D-D fusion reactors, which will ensure a virtually unlimited energy supply. Accurate observations of the neutron flux from such schemes are obtained by using different target materials in the plasma focus.
Keywords:
NUCLEAR AND HIGH-ENERGY PHYSICS
Type:
International Workshop on Energizing Concepts in Advanced Nuclear Energy Systems Analysis; Mar 29, 1978 - Mar 31, 1978; Graz; Austria
Format:
text
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