Spent fuel dissolver critical safety analysis method considering fuel assembly burnup distribution

A criticality safety and fuel assembly technology, applied in the direction of reactor fuel elements, reactors, and greenhouse gas reduction, can solve the problems of not providing criticality safety analysis methods, maximize comprehensive benefits, increase processing capacity, and solve safety and economic problems The contradictory effect of sex

Pending Publication Date: 2021-12-31
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

For example, 201410271524.4 "A Dissolver Criticality Safety Control Method with Annular Solid Neutron Poison Arrangement" and 201410271775.2 "A Discrete Solid Neutron Poison Arrangement Dissolver Criticality Safety

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  • Spent fuel dissolver critical safety analysis method considering fuel assembly burnup distribution
  • Spent fuel dissolver critical safety analysis method considering fuel assembly burnup distribution
  • Spent fuel dissolver critical safety analysis method considering fuel assembly burnup distribution

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Embodiment

[0051] Taking a spent fuel dissolver as an example, how the present invention is applied to criticality safety analysis of spent fuel dissolver is described. The most reactive spent fuel assembly to be processed by the spent fuel dissolver is a 17×17 assembly, which is divided into 18 sections in the axial direction, 235 The U enrichment degree is 4.95%, and its average fuel consumption is 38200MWd / tU. The mass of fuel pellets processed in the spent fuel dissolver is the mass of a whole PWR spent fuel assembly.

[0052] First, for the most reactive spent fuel assembly, the number of radial fuel rods is 264, and the number of axial segments is 18. The normalized relative distribution of burnup in each section of the envelope in the axial direction calculated by the component burnup calculation program is shown in Table 1, and the normalized relative distribution of burnup in each fuel rod in the radial direction is shown in Table 2.

[0053] Table 1

[0054]

[0055]

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Abstract

The invention relates to a spent fuel dissolver critical safety analysis method considering fuel assembly burnup distribution. According to the method, burnup distribution of each axial section of each fuel rod of a maximum reactivity assembly is determined, the mass proportion of fuel in each burnup interval is determined, and the fuel is arranged in a layered mode from inside to outside according to the reactivity of the fuel (the fissile nuclide content), so that the composition of the fuel in a spent fuel dissolver is closer to the real situation, and a certain critical safety analysis conservative margin exists, so that the treatment capacity of the spent fuel dissolver can be improved or the use of neutron poison materials can be reduced under the condition of ensuring safety. According to the method, refined critical safety analysis of the spent fuel dissolver is realized. The method is an advanced spent fuel dissolver critical safety analysis method with engineering feasibility.

Description

technical field [0001] The invention belongs to the field of nuclear criticality safety analysis, and in particular relates to a criticality safety analysis method in a spent fuel dissolver considering the axial and radial burnup distribution of fuel assemblies. Background technique [0002] The dissolver is a key process equipment for the head-end treatment of the reprocessing plant, and its main function is to dissolve the spent fuel cut into short sections. The dissolver is a place where fissile materials are relatively concentrated, and it is the equipment that needs to focus on criticality safety. The dissolution of spent fuel is carried out in the dissolver. Since it is a typical nuclear facility for out-of-reactor operations, processing, and handling of fissile materials, nuclear criticality safety and control occupy a special and important position in its design, operation, and management. However, my country chooses a closed nuclear fuel cycle strategy, and there i...

Claims

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Application Information

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IPC IPC(8): G21C19/42
CPCG21C19/42Y02E30/30
Inventor 于淼邵增易璇杨海峰胡小利陈添张毅诚费钧天郭治鹏张浩然李想
Owner CHINA NUCLEAR POWER ENG CO LTD
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