作者: Debdas Biswas , Roy W. Rathbun , Si Young Lee , Melvin R. Buckner
关键词: Neutron transport 、 Delayed neutron 、 Plutonium 、 Spent nuclear fuel 、 Burnup 、 MOX fuel 、 Nuclear engineering 、 Control rod 、 Nuclear reactor core
摘要: Studies have been conducted to demonstrate that weapons-grade plutonium can be readily disposed of by utilizing it as a fuel in pressurized water reactors (PWR). The disposition achieved first fabricating the into mixed-oxide (MOX) form and then irradiating either advanced or existing PWRs depleted level similar commercial spent fuel. Preliminary neutronics studies pertaining safety-related core design using 100% MOX are presented. results feasibility small reactor 600-MW(electric) capacity called PDR600, large 1,400-MW(electric) PDR1400, typical four-loop modified Westinghouse reactor. Feasible loading patterns obtained for initial equilibrium cycles discrete borosilicate glass burnable absorbers heavy zirconium diboride integral every rod. preliminary physics include information on soluble boron concentration, peaking factors, Doppler moderator reactivity coefficients, boron, xenon control rod worths, shut-down margin delayed neutron parameters. with minimum changes present safety licensing criteria PWRs.