Metallic fast reactor fuel element irradiation test device

A fuel element and test device technology, applied in the field of reactor irradiation, can solve problems such as difficulties in practical application, and achieve the effect of reducing the level of thermal neutron fluence rate and reducing the impact

Active Publication Date: 2019-12-20
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Metal-type fast reactor fuel has a significant growth phenomenon due to irradiation, which brings a series of difficulties to its practical application

Method used

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  • Metallic fast reactor fuel element irradiation test device
  • Metallic fast reactor fuel element irradiation test device
  • Metallic fast reactor fuel element irradiation test device

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Embodiment Construction

[0030] In order to understand the above-mentioned purpose, features and advantages of the present invention more clearly, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be noted that, under the condition of not conflicting with each other, the embodiments of the present application and the features in the embodiments can be combined with each other.

[0031]In the following description, many specific details are set forth in order to fully understand the present invention. However, the present invention can also be implemented in other ways different from the scope of this description. Therefore, the protection scope of the present invention is not limited by the following disclosure. limitations of specific examples.

[0032] Please refer to Figure 1-Figure 3 , the metal type fast reactor fuel element irradiation test device adopts such as figure 1 The structure shown is comp...

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Abstract

The invention discloses a metallic fast reactor fuel element irradiation test device. The device can be used for carrying out neutron irradiation test on metallic fast reactor fuel in a thermal spectrum research reactor and has the functions of neutron spectrum hardening, metallic fuel irradiation temperature control, fuel element heat release power measurement and the like. The device comprises aprotection tube, a cadmium tube, an irradiation test piece, a related gas pipeline, a thermocouple and the like. According to the device, a cadmium metal layer is adopted to absorb thermal neutrons to reduce the thermal neutron flux rate in the device, so that the neutron energy spectrum of a test fuel element is close to that of a fast neutron reactor; and the temperature difference is established between air gaps and a liquid metal layer outside a fuel rod, and the gas components in the air gaps in each irradiation part are independently adjusted, so that the temperature of fuel core bodiesin different irradiation parts are controlled within a required temperature range.

Description

technical field [0001] The invention relates to the technical field of reactor irradiation, in particular to a metal-type fast reactor fuel element irradiation test device. Background technique [0002] Among the 6 reactor types proposed by the Generation IV Nuclear Energy Systems International Forum (GIF), 5 of them adopt the fast neutron spectrum reactor design. The fast neutron reactor is the main reactor type of the future advanced fission energy system, and it undertakes the great expectation of improving the power generation efficiency of the nuclear energy system and significantly improving the utilization rate of uranium resources. If fast neutron reactor technology is combined with advanced fuel reprocessing technology, and finally a closed fuel cycle system is established, it is expected to use the existing proven uranium resource reserves to meet human energy needs for nearly a thousand years. [0003] The research and development of advanced fuel elements is an ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00G21C17/10G21C17/112
CPCG21C17/001G21C17/10G21C17/112Y02E30/30
Inventor 张亮吴红伟杨文华孙胜戴钰冰赵文斌林瑞霄江丽娟屈英前刘洋
Owner NUCLEAR POWER INSTITUTE OF CHINA
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