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Fission neutron converter

A fission neutron converter technology, which is applied in the field of reactor fuel assembly positioning grid out-of-reactor test devices, can solve the problems of large size of neutron converter fuel elements, which is not conducive to improving power density, etc., to achieve increased power, The effect of increasing the neutron fluence rate

Active Publication Date: 2013-09-18
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

The neutron converter fuel element of the JHR stack is too large in size, which is not conducive to improving its power density

Method used

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  • Fission neutron converter

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Embodiment

[0024] Such as figure 1 As shown, the fission neutron converter of the present invention includes an inner casing 7 and an outer casing 3 coaxially fitted with the inner casing 7, and two ends between the inner casing 7 and the outer casing 3 are respectively installed with The upper grid plate 4 and the lower grid plate 8, the upper grid plate 4 and the lower grid plate 8 are exactly the same in structure size, and the upper grid plate 4 and the lower grid plate 8 are provided with 64 fuel rod installation counterbores, The holes are arranged in a triangular lattice and connected by ribs. The number and arrangement of the counterbore holes are calculated based on the mutual coupling calculation of reactor physics and thermal engineering, and the mechanical structure is continuously optimized. The ribs form a rhombic cooling water flow channel. 64 cross-shaped fuel rods 6 are inserted between the upper grid plate 4 and the lower grid plate 8, and a throttle plug 5 is installed...

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Abstract

The invention discloses a fission neutron converter. The fission neutron converter comprises an inner sleeve and an outer sleeve coaxially sleeved with the inner sleeve, wherein an upper grid plate and a lower grid plate are respectively mounted at two end parts between the inner sleeve and the outer sleeve, and cross-shaped fuel rods are mounted between the upper grid plate and the lower grid plate. According to the fission neutron converter disclosed by the invention, the bottleneck problem of material irradiation is solved by adequately utilizing technical conditions of the convention research reactor, the twofold effect can be achieved with half effort, and the current problems that on the one hand, the advanced research reactor cannot be built in one day, and on the other hand, a large amount of in-service research reactors are still operated are solved; by utilizing the cross-shaped fuel rods made of high-fission-density fuels, the fluence rate of local fast neutrons of a reactor core is substantially improved under a condition that the physical and thermotechnical safety of an HFETR (High Flux Engineering Test Reactor) is met, so that the technical potentials of the HFETR effectively are developed, and furthermore, the irradiation cost of materials is saved.

Description

technical field [0001] The invention relates to a device for the out-of-reactor test of a reactor fuel assembly positioning grid, in particular to a fission neutron converter. Background technique [0002] With the development of nuclear energy technology in the world, the requirements for the radiation resistance of materials are getting higher and higher. As the supercritical reactor of the fourth generation of nuclear power, its design pressure is 25MPa and the temperature is 550°C. These performance parameters are far beyond the parameters of all reactor designs so far. It is necessary to study the neutron physical properties of materials in the supercritical state . As the future development direction of energy technology, nuclear fusion has always been a key factor and bottleneck restricting its development. According to design requirements, the material of the first wall of ITER needs to withstand several dpa of fast neutron radiation, DEMO needs to withstand dozens...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C23/00
CPCY02E30/30
Inventor 张平吕仙镜孙寿华杨文华童明炎
Owner NUCLEAR POWER INSTITUTE OF CHINA
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