EPRI Workshop on Evaluation of Engineering Opportunities in Inertial-Confinement Fusion in Existing and Planned Facilities

摘要

Of the top twenty experiments, eight experiments deal with material effects in the reactor environment resulting from interaction with liquid metals, pulsed x-rays and neutrons, and cyclic mechanical loading. Three experiments concern the response of liquid lithium or lead-lithium, when used as free jets or wetting films or when flowing in woven or solid tubes, to rapid volumetric energy deposition and to shocks resulting from the target microexplosion. Two experiments deal with neutronics especially aimed at verification of currently postulateed codes used for target, blanket and shield design. Two experiments address tritium extraction in the presence of impurities which are anticipated especially from ICF target debris. Launching and sensing the velocity and position of targets which must be injected into the reactor chamber is addressed by two experiments. The remaining experiments would examine data needs in the area of of reactor volume clearing time following the microexplosion, laser beam transport through uncleared gas, and formation and stability of plasma channels applicable to light ion beams. (ERA citation 07:045328)