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Method for loading MOX fuel assembly arranged at multiple sub-regions in radial direction

A fuel assembly and multi-partition technology, applied in the direction of reactor fuel elements, nuclear reaction control, nuclear power generation, etc., can solve the problems that are not conducive to the safe operation of the core and the flattening of the core power, so as to improve performance and increase The effect of content

Inactive Publication Date: 2017-01-04
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

For MOX fuel assemblies, UO 2 The fuel assembly is equivalent to a thermal neutron source, resulting in a large power peak at the boundary of the MOX fuel assembly, which is very unfavorable for flattening the power of the core, and even more unfavorable for the safe operation of the core.

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  • Method for loading MOX fuel assembly arranged at multiple sub-regions in radial direction
  • Method for loading MOX fuel assembly arranged at multiple sub-regions in radial direction
  • Method for loading MOX fuel assembly arranged at multiple sub-regions in radial direction

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Embodiment Construction

[0010] The present invention will be described in detail below in conjunction with the accompanying drawings and embodiments.

[0011] The MOX fuel assembly loading method with radial multi-section arrangement provided by the present invention adopts multi-section arrangement for MOX fuel assemblies radially, and the Pu content of each section is different. The principle of partitioning is due to the MOX fuel assembly and UO 2 Differences in energy spectra of fuel assemblies, UO adjacent to MOX fuel assemblies 2 The fuel assembly will become the neutron source of the fuel rods at the edge of the MOX assembly, so it is necessary to reduce the Pu content of the fuel pellets in each area outside the MOX fuel assembly, and increase the Pu content of the fuel pellets in each area inside the assembly to reduce the MOX fuel assembly and UO 2 MOX Fuel Assemblies and UO Caused by Energy Spectrum Interference Effects Between Fuel Assemblies 2 Larger core power crest factor at the fuel...

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Abstract

The invention relates to a method for loading an MOX fuel assembly arranged at multiple sub-regions in the radial direction. The MOX fuel assembly is arranged at the multiple sub-regions in the radial direction, the Pu content at each sub-region is designed and loaded, the Pu content of fuel pellets at the external sub-regions of the assembly is lower than that of fuel pellets at the internal sub-regions of the assembly, and it is guaranteed that the average Pu content of the assembly meets the designing requirement; meanwhile, fuel manufacturing difficulty caused by the type of the fuel pellets is considered to reduce a large core power peak factor, caused by an energy spectrum interference effect between the MOX fuel assembly and a UO2 fuel assembly, at the interface of the MOX fuel assembly and the UO2 fuel assembly, a brand-new MOX fuel assembly radial loading design is achieved, and the performance of the fuel assembly is improved.

Description

technical field [0001] The invention belongs to the MOX fuel loading technology of the pressurized water reactor core, and in particular relates to a loading method of the MOX fuel assembly which is radially arranged in multiple partitions when the MOX fuel is partially loaded in the pressurized water reactor core. Background technique [0002] In a PWR core partially loaded with MOX fuel, the MOX fuel assemblies and UO 2 fuel assembly. The content of Pu in MOX fuel assembly is high, and the neutron spectrum of Pu isotope fission is harder than that of uranium isotope fission, and MOX fuel has a larger thermal neutron absorption cross section, resulting in a harder neutron spectrum of MOX fuel assembly , and UO 2 The neutron spectra of fuel assemblies vary widely. For MOX fuel assemblies, UO 2 The fuel assembly is equivalent to a thermal neutron source, resulting in a large power peak at the boundary of the MOX fuel assembly, which is not conducive to flattening the powe...

Claims

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Application Information

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IPC IPC(8): G21C3/326
CPCG21C3/326G21C3/3265Y02E30/30
Inventor 郭治鹏霍小东刘国明杨海峰
Owner CHINA NUCLEAR POWER ENG CO LTD
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