Molten salt reactor core, molten salt reactor system, fuel cycle system and fuel cycle method

A molten salt reactor and core technology, applied in the field of molten salt reactor core, to achieve the effect of solving the shortage of nuclear fuel resources and the accumulation of high-level radioactive waste, excellent transmutation ability, and excellent thorium-uranium multiplication ability

Active Publication Date: 2018-06-15
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The technical problem to be solved by the present invention is to overcome the lack of a set of molten salt reactor core and molten salt reactor system that can not only transmute the TRU in the spent fuel of the pressurized water reactor but also utilize nuclear fuel thorium in the prior art, and provide a Novel Molten Salt Reactor Core, Molten Salt Reactor System, Fuel Cycle System and Fuel Cycle Method

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  • Molten salt reactor core, molten salt reactor system, fuel cycle system and fuel cycle method
  • Molten salt reactor core, molten salt reactor system, fuel cycle system and fuel cycle method
  • Molten salt reactor core, molten salt reactor system, fuel cycle system and fuel cycle method

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Embodiment 1

[0067] 1. Molten salt reactor core

[0068] Such as figure 1 The molten salt reactor shown has a molten salt reactor core, the active area of ​​the molten salt reactor core has its own independent transmutation zone 10 and multiplication zone 20, and the transmutation zone 10 is set in the multiplication zone 20; the transmutation Zone 10 is used for the fast-spectrum transmutation of transuranic nuclides under the conditions of chloride salts and no moderator, and transfers the high amount of residual neutrons obtained from the transmutation to the breeding zone 20; the breeding zone 20 is used for nuclear fuel thorium in fluorine salts And the hyperthermia proliferation under the condition that the moderator is graphite balls.

[0069] Wherein, a graphite reflective layer 30 is arranged outside the active area.

[0070] Wherein, the transmutation zone 10 and the multiplication zone 20 are arranged coaxially.

[0071] Wherein, the transmutation zone 10 is provided with a f...

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Abstract

The invention discloses a molten salt reactor core, a molten salt reactor system, a fuel cycle system and a fuel cycle method. An active region of the molten salt reactor core has a respective independent transmutation region and a proliferation region, and the transmutation region is disposed in the proliferation region; the transmutation region is used for fast-spectrum transmutation of tran uranium nuclides under chlorine salt and no moderators conditions, and transferring high residual neutrons obtained by the transmutation to the proliferation region; the proliferation region is used forsuperheating-spectrum proliferation of nuclear fuel thorium under fluoride salt and graphite balls as the moderator conditions. The molten salt reactor core, the molten salt reactor system, the fuel circulation system and the fuel cycle method have an excellent thorium uranium proliferation capability and a transmutation capability, can efficiently transmute TRU in spent fuel, fully utilize the nuclear fuel thorium, and successfully solve current difficulties of shortage of nuclear fuel resources and accumulation of highly active wastes in nuclear development.

Description

technical field [0001] The invention relates to a molten salt reactor core, a molten salt reactor system, a fuel circulation system and a fuel circulation method. Background technique [0002] As a clean, low-carbon, high-energy-density energy source, nuclear power has incomparable advantages over other energy sources. At present, my country's nuclear power units are dominated by pressurized water reactors, using U-235, the only fissile material in nature, as the ignition fuel, and adopting a one-pass fuel cycle mode. The spent fuel obtained by this fuel cycle mode still contains unfissioned U-235. 235, U-238, Transuranic (hereinafter referred to as "TRU") and highly radioactive fission products, and the existing technology does not reprocess the spent fuel, but directly stores or buries it. Therefore, the fuel cycle mode has the problems of nuclear waste management caused by high demand for uranium ore, low utilization rate of nuclear fuel and accumulation of high radioacti...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/30G21C21/00
CPCG21C21/00G21F9/308Y02E30/30
Inventor 伍建辉刘亚芬陈金根邹杨
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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