Published December 2020 | Version v1
Journal article

Study on the method for determining the acceptance value of material properties of localized material of nuclear power mechanical equipment

  • 1. Nuclear and Radiation Safety Center, MEE, Beijing (China)

Description

At present, the materials of China's nuclear power mechanical equipment are mostly manufactured and accepted in accordance with European and American nuclear power standards represented by RCC-M and ASME. In order to establish a set of independent material standards suitable for China's industrial level and practice, key technical issues need to be resolved:determination of the acceptance value of material mechanical properties. Based on the research on the determination methods, technical principles and material performance data processing methods of existing material mechanical property acceptance criteria at home and abroad, a method was proposed used to determine the mechanical property acceptance values of domestic materials for nuclear power machinery equipment. According to this method, a preliminary statistical analysis of the mechanical performance data of the domestically produced materials in the reactor core region of the reactor vessel was conducted to obtain the relevant mechanical performance data distribution and data with a certain level of confidence and probability of surpassing. The results of data processing contribute to provide support for the formulation of China's independent material standards. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Safety (Beijing)
Journal Volume
19
Journal Issue
6
Journal Page Range
p. 93-98
ISSN
1672-5360

Optional Information

Notes
6 figs., 1 tab., 6 refs.; http://dx.doi.org/10.16432/j.cnki.1672-5360.2020.06.016