Pressurized water reactor core with plutonium burnup

摘要

979, 937. Controlling nuclear reactors. NUCLEAR MATERIALS & EQUIPMENT CORPORATION. Aug. 13,1962 [Sept. 5,1961], No. 30890/62. Heading G6C. A nuclear reactor fueled with Pu alone, or together with other fissile and/or fertile material, said Pu containing the Pu-240 isotope, is characterised by that the amount of said Pu 240 in the fuel, and/or the moderation of the reactor, is such that the effective neutron cross-section of the Pu- 240 degreases substantially as the time of operation of the reactor increases; said decrease being sufficient to substantially compensate for the loss of reactivity associated with fission product build up during operation. The reactor is therefore operated in that range in which the initial reactivity of the reactor increases as the Pu content decreases, (i.e. is burnt out). Fig. 1 shows a reactor core R comprising a sealed chamber 21 divided into three zones 23, 25 and 27 by the tubular walls 31 and 33. Wall 31 has openings 35 at the bottom and wall 33 has openings 37 at the top. Container 21 is provided with fluid exit tubes 39. Cooling fluid enters into the tube 31 takes the path shown by the arrows and emerges from tubes 39 to pass to a heat exchanger (not shown). Each zone contains fuel elements 41 which in accordance with this invention contain Pu e.g. 78% Pu 239, 12% Pu 240, and 10% Pu 241, and may contain U-238, Th-232, U-235 or U233. The coolant may be water at high temperature (600‹F.) and high pressure (2000 lbs/sq. inch), which water, above or together with heavy water may serve as a moderator. Other possible coolants are liquid metals, e.q. liquid sodium, and graphite and beryllium may be used as the moderator. The main coolant then flows through tubes containing the fuel, and a separate coolant may be provided to cool the moderator. To conserve neutrons in such a reactor then (a) the initial plutonium enrichment of each zone increases from the centre to the periphery of the core, (b) the initial plutonium enrichment is substantially constant throughout the core, but the amount of moderator per unit core volume decreases from the centre to the periphery of the core, or (c) the moderator coolant, which may be the moderator itself, passes successively from zone to zone entering the reactor at the innermost and leaving at the outermost zone. If the purpose is to minimise the decrease of power output from the centre to the periphery of the core then the converse of the above procedures (a), (b), and (c) should be applied. Further improvement in performance, e.g. the minimizing of reactivity variation during operation, may be achieved by varying the neutron temperature (average speed of the neutrons) in the reactor by external means as a function of time during operation of the reactor. The possible said external means include (a) controlling the moderator and/or the coolant temperature; (b) adjusting the moderator properties by intermixing moderators; or (c) adjusting moderator density. Calculations indicate that these reactors will have negative temperature coefficients of reactivity.