A long-period fuel management method for pressurized water reactor core

Abstract

A long-term fuel management method for a reactor core of a pressurized water reactor. In the first cycle, the reactor core adopts a high-leakage loading mode, that is, an assembly with a high degree of enrichment and an assembly with a low degree of enrichment inside the reactor core match and are combined with each other, and a fuel assembly with the highest degree of enrichment is placed at the outermost cycle of the reactor core; and in the subsequent cycle, the reactor core adopts a low-leakage loading mode, that is, each updated new fuel assembly is placed inside the reactor core and is used in cooperation with a burnt-out old assembly, and the burnt-out old fuel assembly is placed at the outermost cycle of the reactor core. The method directly achieves a long-term refuelling design from the first cycle to the balanced cycle, improving the availability and load factor of a power plant, and thereby enhancing the economic benefits of the power plant.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and in particular relates to a long-period fuel management method. Background technique [0002] PWR core fuel management refers to determining the fuel enrichment degree used in the core, the type of burnable poison, and the arrangement of various components and poison in the core from the first cycle to the balance cycle core, so that the reactor The design results of the core meet the nuclear design criteria and the general requirements of the power plant. The quality of fuel management in the core directly affects the economy and safety of the nuclear power plant, and is the basis for subsequent safety analysis or evaluation. Determination of the placement of various components and poisons within the core. [0003] At present, the core fuel management methods of nuclear power plants in service and under construction in China can be summarized into four types: 1) annual refueling desig...

AI Technical Summary

Problems solved by technology

[0005] (1) Since the long-period refueling design from the first cycle cannot be realized directly, further optimization of the economics of the nuclear power plant has not been realized;

[0006] (2) The use of a single enrichment component for the balance cycle is not conducive to flattening the power distribution of the core, and the power peak factor increases accordingly, thereby affecting the safety of the core; on the other hand, the larger power peak factor causes the core average The fuel consumption of unloading is reduced, and the utilization rate of fuel is also deteriorated

Images