Pressurized water reactor nuclear power plant loss of coolant accident radioactive source term evaluation method

Abstract

The invention relates to the field of nuclear radiation safety and particularly relates to a pressurized water reactor nuclear power plant loss of coolant accident radioactive source term evaluation method. The method comprises the following steps: (1) based on reactor equilibrium cycle life end core burden and the release share of radionuclides from the core to a containment atmosphere, the initial radioactivity of radionuclides released to the containment atmosphere by the reactor core is calculated; (2) the radionuclides are divided to three types according to decay types, and according tothe initial value of radionuclides in the containment atmosphere and a generation term and a subduction term during migration and release processes of the radionuclides in the containment, the radioactivity of each radionuclide in the containment atmosphere at different time is classified and calculated; and (3) according to the leakage rate of the containment and the radioactivity of the radionuclides in the containment atmosphere obtain in the second step, the radioactivity of the radionuclides released to the environment is subjected to integral calculation. The calculation method providedin the invention considers a complete nuclide decay chain, and the method is scientific and reasonable and strong in generality.

Description

technical field [0001] The invention relates to the field of nuclear radiation safety, in particular to a method for evaluating radioactive source items of a water loss accident in a pressurized water reactor nuclear power plant. Background technique [0002] The radioactive source item in nuclear power plant accidents is an important input data for assessing the radiation dose received by the public, and it is the focus of attention in nuclear power plant safety analysis and environmental impact assessment. After a loss of water accident (LOCA) in a pressurized water reactor nuclear power plant, the radionuclides in the fuel rods and primary coolant enter the containment gas space, and after a series of processes such as self-decay, deposition, and spray removal, the radionuclides Leakage into the environment through containment, causing radiation hazards to the public and living organisms. The process of radionuclide migration and release in the LOCA accident is as follow...

AI Technical Summary

Problems solved by technology

[0008] The purpose of the present invention is to provide a method for evaluating the radioactive source item of a pressurized water reactor nuclear power plant loss of water accident, to solve the problems of generality and conservatism in the prior art

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