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Title: Examination of the feasibility of a nuclear-pumped laser-driven inertial confinement fusion reactor with magnetically protected walls. Master's thesis

Technical Report ·
OSTI ID:5313837

A preliminary design study of a nuclear-pumped laser-driven inertial confinement fusion reactor with a magnetically protected first wall using an advanced DT-ignited, DD-fueled pellet demonstrated the feasibility of such a concept. This paper presents a parametric study of the required energy multiplication in the blanket, the pellet injection rate, and the net efficiency of this conceptual reactor for advanced pellet yields. A model of the reactor energy balance yields a required energy multiplication of 2.4. A cylindrical design for a helium-cooled blanket demonstrates that natural uranium micropellets in a laser pump region provide a multiplication of 2.9 with a sub-critical neutron multiplication factor of 0.14. A lithium-oxide layeroutside of the laser pump region provides a tritium breeding ratio of up to 0.4, which is more than sufficient to produce enough tritium for advanced DD-fueled, DT-ignited pellets to fuel the reactor. This paper presents the analysis behind these conclusions and presents avenues for further research on this concept. Nuclear-Pumped laser, Inertial confinement fusion reactor tritium breeding ratio, Fission, Criticality.

Research Organization:
Air Force Inst. of Tech., Wright-Patterson AFB, OH (United States)
OSTI ID:
5313837
Report Number(s):
AD-A-248163/8/XAB; AFIT/GNE/ENP-92M-4
Resource Relation:
Other Information: Thesis (M.S.)
Country of Publication:
United States
Language:
English