Optimized fissile and fusile breeding in a laser-fusion fissile-enrichment flux trap blanket

Research output: Contribution to journalArticle

Abstract

Optimization of fissile and fusile production in the SOLASE-H laser-fusion fissile-enrichment fuel-factory blanket is carried out. The objective is maximizing fissile breeding with the constraints of maintaining self-sufficiency in tritium production, and realistically accounting in the modeling for structural and coolant compositions and configurations imposed by the thermal-hydraulic and mechanical designs. The effect of radial and axial blanket zone thicknesses on fusile and fissile breeding is studied using a procedure which modifies the zones' effective optical thicknesses, rather than the actual three-dimensional geometrical configurations. A tritium yield per source neutron of 1.08 and a Th (n, γ) reaction yield per source neutron of 0.43 can be obtained in such a concept, where ThO2 Zircaloy-clad fuel assemblies for light water reactors (LWRs) are enriched in the233U isotope by irradiating them in a lead flux trap. This corresponds to 0.77 kg/[MW(th)-year] of fissile fuel production, and 1.94 years of irradiation in the fusion reactor to attain an average 3 w/o fissile enrichment in the fuel assemblies. For a once-through LWR cycle, a support ratio of 2-3 is estimated. However, with fuel recycling, more attractive support ratios of 4-6 may be attainable for a conversion ratio of 0.55, and of 5-8 for a conversion ratio of 0.70. These estimates are lower than those reported, around 20, for related designs.

Original languageEnglish (US)
Pages (from-to)285-298
Number of pages14
JournalJournal of Fusion Energy
Volume1
Issue number3
DOIs
StatePublished - Jul 1 1981

Fingerprint

Laser fusion
laser fusion
blankets
traps
light water reactors
Fluxes
neutron sources
tritium
Light water reactors
assemblies
Neutron sources
fissile fuels
Tritium
fuel production
fusion reactors
coolants
recycling
configurations
industrial plants
hydraulics

Keywords

  • Fusion reactors
  • Monte Carlo method
  • breeding blankets
  • breeding ratio
  • hybrid reactors
  • three-dimensional calculations

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Optimized fissile and fusile breeding in a laser-fusion fissile-enrichment flux trap blanket. / Ragheb, Magdi.

In: Journal of Fusion Energy, Vol. 1, No. 3, 01.07.1981, p. 285-298.

Research output: Contribution to journalArticle

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