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Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof

A fuel mixing and operating method technology, applied in thermal reactors, nuclear reactors, climate sustainability, etc., can solve the problems of weak Th neutron breeding ability, low multiplying envelope energy magnification, and poor neutron economy, and achieve optimization The effect of neutron multiplication and utilization process, improving neutron economy and high utilization rate

Active Publication Date: 2014-06-25
TSINGHUA UNIV
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  • Application Information

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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

Method used

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  • Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof
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  • Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof

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Embodiment Construction

[0039] The present invention provides a Th-U self-sustaining cycle fully molten salt fuel mixed reactor system and its operation method. The present invention will be further described below in conjunction with the accompanying drawings and specific implementation methods.

[0040] A Th-U self-sustaining circulation fully molten salt fuel hybrid reactor system, the hybrid reactor system is composed of fast fission breeder reactor and thermal fission reactor, both of which are clad structures, and in the hybrid reactor system are Uniformly cross-arranged connected settings;

[0041] Wherein the cladding of the fast fission breeder reactor is from the inside to the outside, and the fuel zone I, the molten salt fuel breeding zone II and the cladding shielding zone III of the fast fission breeder reactor are arranged in sequence and connected in sequence; the fuel zone I is composed of a plurality of natural The uranium fuel layer 1 and a plurality of coolant layers 2 are alternat...

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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...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C1/02G21C1/04
CPCY02E30/30
Inventor 周志伟肖思聪赵晶杨永伟盛选禹
Owner TSINGHUA UNIV
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