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The invention relates to a classification management method for reactor internal components of a pressurized water reactor nuclear power plant

A technology of classified management and internal components, applied in data processing applications, instruments, resources, etc., can solve problems such as being in a blank state, and achieve the effect of high applicability, strong executable, and clear requirements for supplementary inspections

Inactive Publication Date: 2019-03-26
SUZHOU NUCLEAR POWER RES INST +4
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

At present, my country has not yet established an RVI aging management system, especially during the period of continuous operation of the license after the initial design period of the nuclear power plant, the aging management requirements of RVI (such as aging state assessment, testing requirements, etc.) are still in a blank state

Method used

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  • The invention relates to a classification management method for reactor internal components of a pressurized water reactor nuclear power plant
  • The invention relates to a classification management method for reactor internal components of a pressurized water reactor nuclear power plant
  • The invention relates to a classification management method for reactor internal components of a pressurized water reactor nuclear power plant

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Embodiment 1

[0058] This embodiment manages the radiation-accelerated stress corrosion cracking mechanism of coaming-formed plate bolts in the process of classified management of reactor internal components. Specific steps are as follows:

[0059] 1) Determine the structural list of internal components of a nuclear reactor in my country, and confirm that the coaming-formed plate bolt (BFB) is a component of the reactor. The chemical composition of the component material is Cr (17.28%), Ni (11.65%), Mo (2.49%), Mn (1.24%), Cu (0.46%), Si (0.340%), C (0.038%), Co ( 0.010%), P (0.008%), S (0.003%) and Fe (the balance), which are typical 316 austenitic stainless steels. Between 360°C, the stress can reach up to 630MPa or more. According to the above parameters and referring to NRC NUREG-1801, the potential aging mechanisms of internal components are determined to include stress corrosion cracking, radiation-accelerated stress corrosion cracking, wear, fatigue, thermal aging embrittlement, radi...

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Abstract

The invention provides a classification management method of reactor internal components of a pressurized water reactor nuclear power plant, comprising the following steps: 1) determining an aging mechanism of reactor internal components; 2) determining screening criteria of components; 3) classifying that components in the reactor into A-type component and non-A-type components; 4) carrying out FMECA analysis on non-A-type components, further classify into A, B and C-type components; 5) carrying out functional evaluation on that C-type components, and confirm whether the C-type components aremaintained in the C-type component or are adjusted to the B-type components; 6) dividing that class B and the clas C parts into main inspection parts, enlarging the inspection part, existing outlineparts, and classifying the clas A parts as inspection parts without additional measures; 7) for that main inspection component, the enlarged inspection component and the existing outline component, the classification management method of the invention overcomes the problems of lacking theoretical basis in the management of the conventional reactor inner component components and lacking quantitative analysis in the analysis and evaluation process, and has the advantages of strong executability, high applicability and definite supplementary inspection requirements.

Description

technical field [0001] The invention belongs to the technical field of aging management of internal components of nuclear power plants, and in particular relates to a classification management method for reactor internal components of a pressurized water reactor nuclear power plant. Background technique [0002] Reactor internals (RVI) are key equipment related to nuclear safety (LS level) in nuclear power plants. They have key functions such as supporting and fixing core components, and are directly related to the operational safety and efficiency of the reactor. The establishment of RVI aging management method is an important technical means to ensure the reliability of RVI, and it is also the core component of the aging evaluation system of reactor internal components. At present, my country has not yet established an RVI aging management system, especially during the period of continuous operation of the license after the initial design period of the nuclear power plant,...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06Q10/10G06Q10/06G06Q50/06
CPCG06Q10/0639G06Q10/103G06Q50/06
Inventor 徐超亮王勇薛飞陈志林黄平安英辉郭迪刘向兵池志远王春辉
Owner SUZHOU NUCLEAR POWER RES INST
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