Fuel management method of pressurized water reactor core formed by 177 fuel assemblies

A fuel assembly and fuel management technology, which is applied in the field of fuel management of pressurized water reactor cores, can solve problems such as failure to quickly realize long-term refueling of power plants, and failure to improve the availability of power plants. Utilization and load factor, smooth process, and the effect of ensuring safety

Inactive Publication Date: 2015-12-09
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] To sum up, its disadvantages are: due to the failure to achieve the goal of long-term refueling of the power plant, the availability

Method used

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  • Fuel management method of pressurized water reactor core formed by 177 fuel assemblies
  • Fuel management method of pressurized water reactor core formed by 177 fuel assemblies

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Embodiment

[0030] This embodiment is aimed at a reactor core of a mega-kilowatt nuclear power plant, and the core is composed of 177 fuel assemblies. For the fuel management of a complete nuclear power plant core, the core loading mode of a series of core fuel cycles from the first cycle to the balance cycle should be determined in an overall manner according to the established objectives and given core parameter constraints or guidelines, and Perform relevant neutron physics calculations. The specific content covers: the determination of the enrichment degree of several different fuels used in the first cycle, the determination of the enrichment degree of the new fuel assembly in the subsequent cycle, the selection of the solid burnable poison type in each cycle, and the arrangement of the core fuel assembly and the solid burnable poison and optimization, preliminary safety evaluation, etc.

[0031] For the loading of the first cycle core, three different fuel assemblies with a certain...

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Abstract

The invention discloses a fuel management method of a pressurized water reactor core formed by 177 fuel assemblies. The method comprises the following steps: in the first cycle, fuel assemblies with three different enrichment degrees are adopted, the fuel assemblies are arranged in a high-leakage loading mode, and the cycle length of the first cycle is designed to be annual reloading; in the second cycle, the enrichment degree of reloaded new fuel assemblies is between that of the fuel assemblies in the first cycle and that of balance cycle new fuels; the enrichment degree of the reloaded new fuel assemblies is same to or greater than that of the second cycle new fuels from the third cycle to balance cycle in order to realize 18-months long cycle reloading design; and from the second cycle, core loading adopts a low-leakage loading mode. The method smoothly realizes transition of first cycle annular reloading to balance cycle 18-months long cycle reloading, guarantees the core safety of the first cycle, fast transmits to long cycle reloading design, and improves the utilization rate and the load factor of a power plant.

Description

technical field [0001] The present invention relates to the technical field of pressurized water reactor core fuel management, and in particular relates to a fuel management method for a pressurized water reactor core composed of 177 fuel assemblies, which is used to guide the fuel enrichment degree of a pressurized water reactor nuclear power plant reactor The determination, selection of burnable poisons and arrangement of components in the core. Background technique [0002] PWR core fuel management generally refers to determining the enrichment of fuel used in the core, the concentration of combustible poisons, etc. The type and arrangement of various components and poisons in the core, etc., make the design results of the reactor core meet the nuclear design criteria and the overall requirements of the power plant. The quality of core fuel management directly affects the economy and safety of nuclear power plants, and is the basis for subsequent safety analysis or evalu...

Claims

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Application Information

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IPC IPC(8): G21C7/30
CPCY02E30/30
Inventor 刘启伟李庆陈长周金满吴磊李向阳于颖锐
Owner NUCLEAR POWER INSTITUTE OF CHINA
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