A th-u self-sustaining cycle fully molten salt fuel hybrid reactor system and its operation method

Abstract

The invention belongs to the field of cladding designs of a fusion and fission hybrid reactor, and particularly relates to a Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and an operation method thereof. The Th-U self-sustaining circulating full fused salt fuel hybrid reactor system is characterized in that a fast fission breeder reactor provides an initial easily fission fuel required by starting of a thermal fission reactor, a cladding design of the thermal fission reactor utilizes an arrangement strategy of a seed-cladding to improve the entirety neutron economy of the system, and the purposes of a high energy enlargement factor of the system, tritium breeding and thorium-uranium self-sustaining circulating of the system are realized; <233>U is loaded in an energy generating region, so that the energy generating region has a good neutronics property and is mainly used for realizing the purposes of energy amplification of the system, neutron multiplication and most <233>U breeding of the system; superfluous neutrons enter a tritium producing region and are used for tritium breeding and part of <233>U breeding of the system. According to the hybrid reactor, due to self-sustaining circulating of thorium and uranium, a thorium fuel is converted into <233>U and is gradually burn up in an operation process, and the Th-U self-sustaining circulating full fused salt fuel hybrid reactor system can effectively and stably operate for a long time just by gradually adding the thorium fuel and removing the generated fission product.

Description

technical field [0001] The invention belongs to the cladding design field of fusion and fission hybrid energy reactors, and in particular relates to a Th-U self-sustaining circulation fully molten salt fuel hybrid reactor system and an operating method thereof. Background technique [0002] Proven thorium reserves on Earth are approximately three times those of uranium, and breeding or conversion through advanced reactors will 232 Th is converted to 233 U will greatly increase the storage capacity of existing nuclear fuel resources. In the late 1960s, the nuclear energy community proposed the idea of ​​using a fusion-fission hybrid reactor to breed nuclear fuel, that is, to load depleted uranium, natural uranium or natural thorium fuel outside the fusion device as a breeding layer, and use the high-energy neutrons produced by the fusion reaction to breed nuclear fuel. The nuclear fuel is multiplied in the layer, and the production capacity is output. The multiplied fuel ca...

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Problems solved by technology

[0004] A key problem facing the design of thorium-containing subcritical cladding is: for 232 Th fuel, the threshold energy of its fission reaction is as high as 1MeV, and the thermal neutron absorption cross section is close to 238 3 times U, that is 232 Th's neutron multiplication ability is very weak, neutron economy is poor

The studies on several thorium-based hybrid reactors mentioned above show that the energy magnification M of the pure Th-based hybrid reactor breeder cladding is relatively low, about 2. In order to realize the output of production capacity and the early application of fusion energy, a relatively high demand for fusion power will be proposed. big challenge

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