process for the treatment of fuel in a nuclear reactor using uranium thorium cycle and regeneration reactor for implementing the method

摘要

1,103,669. Nuclear reactors. GENERAL DYNAMICS CORPORATION. 11 May, 1966 [17 May, 1965], No. 20797/66. Heading G6C. A method of fuel management for a nuclear reactor utilizing a thorium-uranium 233 breeding cycle comprises charging the reactor core with fuel units containing uranium and thorium, operating the reactor for the desired reactivity life of at least a portion of the fuel units, removing said portion of the fuel units and reprocessing them to eliminate fission products and recover bred uranium, and refuelling the reactor core with bred uranium, thorium, and make-up plutonium for a subsequent reactor cycle. The method may be applied to a hightemperature graphite-moderated helium-cooled reactor, the core of which is charged initially with thorium and U235-enriched uranium ceramic fuel in the form of carbide or oxide particles uncoated or coated with pyrolytic graphite. The fuel may be contained in parallel channels in a cylindrical graphite moderator body as described in Specification 1,076,549. A central channel may contain additional moderator in the form of beryllium oxide or carbide. Composite particles of uranium and thorium carbides may be used as the fuel or, alternatively, the fuel may be segregated into uranium carbide and thorium carbide particles of different particle sizes to facilitate later separation. At half yearly intervals, for example, some of the fuel elements are removed and reprocessed, being replaced in the reactor by elements containing plutonium carbide or oxide mixed with bred uranium 233 and reprocessed or fresh thorium.