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Design method for containment integrity test of advanced pressurized water reactor nuclear power plant

A design method and containment technology, applied in nuclear power generation, reactors, nuclear engineering, etc., can solve problems such as unreasonable pressure ladder design, long continuous ladder test, imperfect design of buck-boost curve, etc., to ensure safety and enforceability, the effect of ensuring legality

Active Publication Date: 2021-07-20
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, due to the differences in the standards followed and the design of containment structures and functions, there are large differences in the design of the integrity test of each nuclear reactor type containment in terms of depressurization rate, pressure step and duration, and test content of each step. There may be adverse effects such as unreasonable design of the pressure ladder, too long continuous test of the ladder, or imperfect design of the buck-boost curve.

Method used

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  • Design method for containment integrity test of advanced pressurized water reactor nuclear power plant
  • Design method for containment integrity test of advanced pressurized water reactor nuclear power plant
  • Design method for containment integrity test of advanced pressurized water reactor nuclear power plant

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Embodiment 1

[0073] For details, see figure 1 , for the following description.

[0074] (1) Combing of containment boundary penetrations and process pipelines

[0075] Based on the requirements of my country's nuclear safety regulations, guidelines and standards, combined with the structural design of the reactor type containment, all the process pipelines and penetrations penetrating the containment were sorted out, and the configuration of each process pipeline and penetrations was analyzed in the form of a list and function. The formation list is shown in Table 1:

[0076] Table 1 List of containment penetrations of a third-generation advanced PWR in my country

[0077]

[0078] (2) Design of prerequisites for containment integrity test

[0079] According to the combing results of the process pipelines and penetrating parts penetrating the containment, combined with the test implementability and accuracy requirements, the boundary state requirements are designed to form the test p...

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Abstract

The invention relates to the field of nuclear power design, in particular to a design method for a containment integrity test of an advanced pressurized water reactor nuclear power plant. The design method for the containment integrity test of the advanced pressurized water reactor nuclear power plant comprises the following steps: S1, carding a containment vessel boundary penetration piece and a process pipeline; S2, designing a precondition for realizing integrity of the containment; S3, designing a test project based on containment function requirements; S4, performing pressure step design and boost-buck rate design of the integrity of the containment; and S5, forming an advanced pressurized water reactor nuclear power unit containment integrity test scheme design. According to the invention, the safety and the feasibility of the test are ensured to the greatest extent, and meanwhile, the method plays a great positive role in improving the availability of the nuclear power plant.

Description

technical field [0001] The invention relates to the field of nuclear power design, in particular to a design method for the containment integrity test of an advanced pressurized water reactor nuclear power plant. Background technique [0002] As the last barrier to limit the release of radioactive substances to the environment, the containment of the PWR nuclear power plant is responsible for the safety of containing radioactive substances, shielding radiation, and protecting the reactor from external natural events and man-made events under normal operation and accident conditions. Features. The design of the containment shall ensure that any radioactive release from the nuclear power plant to the environment is kept as low as reasonably feasible, and does not exceed the regulatory discharge limit for radioactive release under operating conditions, and does not exceed the possible radioactive release under accident conditions. Accept the limit. Moreover, based on the oper...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/003G21C17/00
CPCG21C17/003G21C17/002Y02E30/30G21D3/001G01M3/2815
Inventor 邢继田齐伟赵侠孙涛刘勇尚臣吴希盼郑仕建陈伟
Owner CHINA NUCLEAR POWER ENG CO LTD
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