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Method for simplifying analysis of elastic-plastic fractures of RPV under extreme accident conditions based on RCC-M specification

An analysis method and technology for accident conditions, applied in the direction of analyzing materials, strength characteristics, measuring devices, etc., can solve the problems of simple form and lack of theoretical basis, and achieve the effect of improving accuracy and expanding the scope of application

Inactive Publication Date: 2017-08-18
SUZHOU NUCLEAR POWER RES INST +4
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Problems solved by technology

Although the later version of the RCC-M code expanded the scope of application of the stress intensity factor plastic correction formula, its form is too simple and lacks a clear theoretical basis

Method used

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  • Method for simplifying analysis of elastic-plastic fractures of RPV under extreme accident conditions based on RCC-M specification
  • Method for simplifying analysis of elastic-plastic fractures of RPV under extreme accident conditions based on RCC-M specification
  • Method for simplifying analysis of elastic-plastic fractures of RPV under extreme accident conditions based on RCC-M specification

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Embodiment 1

[0055] RPV core area inner diameter Ri=1994.5mm, shell wall thickness t=200mm, surfacing layer thickness t c = 7.5 mm. The analysis process of simplified elastic-plastic fracture mechanics under an extreme accident condition is given here. Under an extreme accident condition, the RPV is rapidly cooled to room temperature under normal operating conditions. At the initial moment of the extreme accident, the internal pressure load was 15.5MPa, and the average temperature of the RPV cylinder was 300°C.

[0056] 1) Load analysis

[0057] Under this extreme accident condition, the RPV core barrel bears internal pressure load and thermal shock load, in which the internal pressure load belongs to the primary load, and the thermal shock load belongs to the secondary stress load.

[0058] 2) Defect characterization

[0059] Characterization of RPV defects according to the RCC-M specification, figure 2 To characterize the defect at the RPV core barrel, the defect is an axial crack ...

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Abstract

The invention relates to a method for simplifying analysis of elastic-plastic fractures of a reactor pressure vessel (RPV) under extreme accident conditions based on RCC-M specification. The method comprises the following steps: (a) analyzing loads of extreme accident conditions and dividing various loads into primary stress loads and secondary stress loads by determining whether the loads have influence on plastic instability of the structure; (b) determining types and shape parameters of fissures according to RCC-M specification; (c) obtaining material property parameters of RPV and calculating a linear elastic stress intensity factor, wherein the linear elastic stress intensity factor is sum of stress intensity factors caused by the primary stress loads and the secondary stress loads in transient state; and (d) judging whether the RCC-M specification is applied to plastic correction of the linear elastic stress intensity factor, assessing by using the technology when the plastic correction of the linear elastic stress intensity factor exceeds the application range of the RCC-M specification so as to improve accuracy of analysis of fracture-containing defects of RPV.

Description

technical field [0001] The invention belongs to the technical field of structural integrity assessment, and specifically relates to a simplified elastoplastic fracture mechanics analysis method for crack-like defects in reactor pressure vessels (RPV) under extreme accident conditions, providing accurate technical basis for safety assessment of key nuclear power equipment. Background technique [0002] Reactor pressure vessel (RPV) is a first-class component of nuclear safety. During service, due to the influence of neutron radiation, the material properties will gradually deteriorate; at the same time, RPV will inevitably appear in the process of manufacturing, installation and service. These factors will have a serious impact on the safe operation of nuclear power plants. Therefore, an accurate assessment of the reliability of defective RPVs is required. [0003] At present, linear elastic fracture mechanics analysis is mainly carried out in structural integrity assessment...

Claims

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Application Information

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IPC IPC(8): G01N3/00
CPCG01N3/00G01N2203/0062G01N2203/0682
Inventor 陈明亚余伟炜陈志林薛飞钱贵安吕峰黄平王俊池志远安英辉
Owner SUZHOU NUCLEAR POWER RES INST
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