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Physics and engineering design constraints on fusion-fission hybrids

Physics and engineering design constraints on fusion-fission hybrids

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Some insight into the physics and engineering constraints on FFHs can be obtained from relatively simple physics models of global neutron and plasma power balance computational models and models of technological constraints [19-21,26,28-30,32,33] that serve to illustrate how (tokamak) physics and technology limits/constrains the fusion neutron source strength and the level of auxiliary power needed for the neutron sources. We illustrate this by calculating the total neutron population in a nuclear reactor with an external fusion neutron source S using the so-called "point kinetics" model describing the dynamics of the total neutron population "n" in a nuclear reactor with an external source S. Extensions to more sophisticated models are readily envisioned.

Chapter Contents:

  • 20.1 Input electrical power requirement
  • 20.2 Comparison of waste thermal energy
  • 20.2.1 Comparison of plant electrical energy gain
  • 20.2.2 Limitations on fusion neutron source capabilities for transmutation reactors
  • 20.2.3 Radiation damage limits to the first wall
  • 20.2.4 Thermal limits to the first wall
  • 20.2.5 Tokamak physics limits
  • 20.2.6 Engineering limits on a tokamak fusion neutron source

Inspec keywords: fusion reactor design; hybrid reactors; Tokamak devices; plasma transport processes; fusion reactor theory; neutron sources; nuclear engineering computing

Other keywords: sophisticated models; fusion-fission hybrids; relatively simple physics models; nuclear reactor; total neutron population; auxiliary power; fusion neutron source strength; plasma power balance computational models; engineering design constraints; external fusion neutron source; global neutron; engineering constraints

Subjects: Fusion reactor theory and design; Fission + fusion systems; Neutron sources; Nuclear reactors; Particle beam production and handling; targets; Computing for fission reactor theory and design; Plasma in torus (stellarator, tokamak, etc.)

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