Effects of spectral shifting in an inertial confinement fusion system

The main objective is to study the effects of spectral shifting in an inertial confinement system for kT/shot energy regime on the breeding performance for tritium and for high quality fissile fuel. A protective liquid droplet jet zone of 2 m thickness is used as coolant, energy carrier, and breeder...

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Bibliographic Details
Published inKerntechnik (1987) Vol. 70; no. 4; pp. 233 - 242
Main Authors Şahin, S., Şahin, H. M., Yildiz, K., Acir, A.
Format Journal Article
LanguageEnglish
Published München De Gruyter 01.08.2005
Hanser
Subjects
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Nuclear fuels
Electric power plant
Breeder
Coolant
Tritium
Droplet
Helium
Displacement
Heavy metal
Nuclear reactor
Thickness
Inertial confinement
Performance
Plutonium 239
Radiation damage
Inertial confinement fusion
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Summary:The main objective is to study the effects of spectral shifting in an inertial confinement system for kT/shot energy regime on the breeding performance for tritium and for high quality fissile fuel. A protective liquid droplet jet zone of 2 m thickness is used as coolant, energy carrier, and breeder. Flibe as the main constituent is mixed with increased mole-fractions of heavy metal salt (ThF or UF ) starting by 2 moles% up to 12 moles%. Spectrum softening within the inertial confinement system reduces the tritium production ratio (TBR) in the protective coolant to a lower level than unity. However, additional tritium production in the Li DT zone of the system increases TBR to values above unity and allows a continuous operation of the power plant with a self-sustained fusion fuel supply. By modest fusion fuel burn efficiencies (40 to 60 %) and with a few mol.% of heavy metal salt in the coolant in form of ThF or % UF , a satisfactory TBR of > 1.05 can be realized. In addition to that, excess fissile fuel of extremely high isotopic purity with a rate of ∼ 1000 kg/year of U or Pu can be produced. Radiation damage through atomic displacements and helium gas production after a plant operation period of 30 years is very low, namely dpa < 1 and He < 2 ppm, respectively.
ISSN:0932-3902
2195-8580
DOI:10.3139/124.100251