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A Method for Evaluating the Radioactive Source Term of a Loss of Water Accident in a Pressurized Water Reactor Nuclear Power Plant

A loss of water accident, radioactive source technology, applied in the field of nuclear radiation safety

Inactive Publication Date: 2021-08-20
NUCLEAR & RADIATION SAFETY CENT
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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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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  • A Method for Evaluating the Radioactive Source Term of a Loss of Water Accident in a Pressurized Water Reactor Nuclear Power Plant
  • A Method for Evaluating the Radioactive Source Term of a Loss of Water Accident in a Pressurized Water Reactor Nuclear Power Plant
  • A Method for Evaluating the Radioactive Source Term of a Loss of Water Accident in a Pressurized Water Reactor Nuclear Power Plant

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Embodiment Construction

[0070] The present invention will be further described below in conjunction with the accompanying drawings and specific embodiments.

[0071] A method for evaluating the radioactive source item of a pressurized water reactor nuclear power plant loss of water accident provided by the present invention mainly includes the following steps:

[0072] (1) Calculation of the initial activity of nuclides released from the core into the containment atmosphere

[0073] Consider that the radionuclides in the gap between the core fuel pellets and the cladding are instantly released into the containment and mixed uniformly. The initial value of the radionuclide activity released from the core to the containment is obtained by multiplying the core stock at the end of the reactor equilibrium cycle life by the release share of each nuclide from the core to the containment atmosphere. Species distribution, multiplied by the percentages of species corresponding to molecular iodine, organic iod...

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Abstract

The present invention relates to the field of nuclear radiation safety, in particular to a method for assessing radioactive source items in pressurized water reactor nuclear power plant loss of water accidents. Calculate the initial radioactivity of the nuclides released from the reactor core to the containment atmosphere; (2) Divide the nuclides into three categories according to their decay types. The initial value and the production and depletion items of nuclides in the process of containment migration and release are used to classify and calculate the radioactivity of each nuclide in the containment atmosphere at different times; (3) According to the containment leakage rate and step (2), get The radionuclide activity in the containment atmosphere is integrated to calculate the radionuclide activity released into the environment. The calculation method provided by the invention considers the complete nuclide decay chain, is scientific and reasonable, and has strong versatility.

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...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06Q10/06G06Q50/06
CPCG06Q10/0635G06Q50/06
Inventor 陈海英陈妍郭瑞萍王韶伟靖剑平韩静茹攸国顺刘福东张春明
Owner NUCLEAR & RADIATION SAFETY CENT
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