Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241

A solution reactor and solution technology, applied in the field of solution reactor, can solve the problems of reducing the conversion ratio of uranium-238 to plutonium-239, uneconomical problems, etc., and achieve the effects of reduced loading, high safety and high economy

Active Publication Date: 2011-02-09
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

Since the realization of transmutation consumes a large amount of neutrons, taking a fast reactor as an example, the transmutation of neptunium-237 (or americium-241) will inevitably reduce the conversion ratio of uranium-238 to plutonium-239, and expensive devices are used to perform neptunium-237 (or americium-241) transmutation is not economical

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  • Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241
  • Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241

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Embodiment Construction

[0026] The present invention is further described below:

[0027] The solution pile of the present invention uses plutonium (or plutonium+americium) solution as fuel and neptunium solution as a target to form a solution pile for burning plutonium and neptunium transmutation, wherein the concentration of plutonium is 50-200g / L.

[0028] The neutron chain reaction of the solution reactor of the present invention is carried out in a closed reactor container filled with plutonium nitrate (or plutonium+americium) aqueous solution. During the reaction, the gas fission product xenon in the solution pile runs out of the solution, which reduces the loss of reactivity of the xenon-135 toxin. Other fission products (such as neutron poisons) produced by plutonium fission can be continuously or intermittently removed from the solution with inorganic ion exchange resins. In order to maintain the reactivity of the core, new plutonium solution or a mixed solution of plutonium, americium and ...

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Abstract

The invention discloses a solution reactor used for the plutonium combustion and the neptunium-237 or the americium-241 transmutation. The solution reactor adopts plutonium or plutonium and americium in the spent fuel of the nuclear power plant as the fuel, and adopts neptunium-237 or americium-241 as the target. By adopting the solution reactor, the minor actinides which have long half life and high toxicity and can not be stored for a long time, such as the neptunium-237 or the americium-241, can be changed into nuclides with short half life and low toxicity through transmutation. Because the solution reactor adopts the spent fuel and can generate electricity at the low temperature, the cost-effectiveness and the security are high; the neutron provided by the plutonium combustion can extract plutonium-238 from the neptunium-237 solution target as the isotope battery, thereby the inexpensive energy is provided; the americium-242m extracted from the americium-241 solution target can be widely applied to the aerospace industry and the medical industry.

Description

technical field [0001] The invention relates to a nuclear reactor, in particular to a solution reactor for plutonium incineration and neptunium-237 (or americium-241) transmutation. Background technique [0002] The development of nuclear power inevitably involves the reprocessing of spent nuclear fuel. On the issue of spent fuel reprocessing, transmutation can be considered as a process in which a nuclide changes its nuclear structure and becomes another nuclide. From the perspective of spent fuel processing, it refers to the transformation of plutonium, other actinides, and fissile nuclides with long half-lives into other nuclides with good properties. Because neptunium-237 or americium-241 and other minor actinide nuclides have long half-lives and high toxicity, they cannot be stored for a long time, and transmutation must be used to form nuclides with short half-lives and low toxicity. According to the physical characteristics that transmutation consumes a large amount...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21G1/02
Inventor 吴英华李茂良钱积惠王连杰牛文华李大图
Owner NUCLEAR POWER INSTITUTE OF CHINA
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