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Forecast evaluation method of radiation embrittlement of reactor pressure vessel

A technology of pressure vessels and reactors, which is applied in the direction of instruments, special data processing applications, electrical digital data processing, etc., and can solve problems such as poor stability and inaccurate data collection model parameter settings

Active Publication Date: 2013-02-13
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, due to insufficient data collection and inaccurate model parameter settings, the CIAE2009 model formula performed poorly in calculation stability, so the model formula was revised and improved on the basis of this model, and CM-1201 was developed.

Method used

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  • Forecast evaluation method of radiation embrittlement of reactor pressure vessel
  • Forecast evaluation method of radiation embrittlement of reactor pressure vessel
  • Forecast evaluation method of radiation embrittlement of reactor pressure vessel

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Experimental program
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Embodiment

[0058] The nuclear power plant uses A508-III material as the reactor pressure vessel material, the design service life is 40 full power years, and the allowable adjustment reference temperature ART at the end of the service life is 85°C. The specific chemical compositions of the materials are listed in Table 1. The T measured by the Charpy impact test of the unirradiated A508-III base metal 41J -47°C, RT NDT =-20°C, RT NDT The measurement accuracy is σ I =7°C, after the pressure vessel has operated with the stack for a long time, T 41J The temperature became -20°C. The manufacturing process of pressure vessels is forging. The average operating temperature of the reactor at full power is 290°C. After 20 years of full power operation, the fast neutron fluence at the 1 / 4 wall thickness of the pressure vessel from the inner surface was determined to be 2.99×10 19 n / cm 2 , the neutron fluence rate is 3.95×10 10 n / (cm 2 .s ec), the T measured by the Charpy impact test of t...

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Abstract

The invention belongs to the technical field of security evaluation of a reactor pressure vessel (RPV) of a nuclear power plant and specifically relates to a forecast evaluation method of radiation embrittlement of an RPV. According to the method, on the basis that RPV bombardment damage mechanisms are understood, experience of international correlation models is obtained; and further, due to the fact that contents of copper (Cu) in domestic RPV materials are low, contribution functions of non Cu element precipitated phase (Solute-Atom Cluster) on irradiation hardening are introduced into a calculation formula, the contribution functions are ignored by each forecast module all the time, and finally a calculation model containing a non Cu element precipitated phase mechanism is formed.

Description

technical field [0001] The invention belongs to the technical field of safety assessment of nuclear power plant pressure vessels, and in particular relates to a method for predicting and assessing radiation embrittlement of reactor pressure vessels. Background technique [0002] Reactor pressure vessel (RPV), as a pressure-bearing part of the primary circuit, is the core equipment in the pressurized water reactor nuclear power plant, and it is also the non-replaceable core equipment in the nuclear power plant. Its service life determines the service life of nuclear power plants and directly affects the economy and safety of nuclear power plants. All countries in the world pay great attention to the aging management and life assessment of pressure vessels. RPV is generally made of ferritic low-alloy steel, which has a body-centered cubic structure and is characterized by low-temperature brittleness. Due to the harsh service environment of the material and the joint action of...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F19/00
Inventor 佟振峰林虎杨文
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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