T/CNS 12-2019 Active Group standards

T/CNS 12-2019 The environmental fatigue impact model of metal materials in pressurized water reactor nuclear power plants

T/CNS 12-2019 The environmental fatigue impact model of metal materials in pressurized water reactor nuclear power plants

Publish Date: 2019-05-27 Implement Date: 2019-09-01 For services related to genuine standard inquiry, procurement, translation, and other related services in China, please Contact Us
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Basic Information

Standard Code: T/CNS 12-2019
Standard Type: Group standards
Standard Status: Active
is_force_gb: no
CCS Name: \nTest methods for the physical and chemical properties of metals
ICS Name: Comprehensive Testing of Metal Materials
Publish Date: 2019-05-27
Implement Date: 2019-09-01

Scope

Scope: This standard provides an environmental fatigue impact model for low-alloy steel, austenitic stainless steel, and nickel-based alloys in pressurized water reactor nuclear power plants. This standard applies to the environmental fatigue design, environmental fatigue damage assessment, and lifetime evaluation of components in the primary pressure boundary of pressurized water reactor nuclear power plants. Main technical content: In the preparation of this section, reference was made to the Metal Research Institute's enterprise standard "Q/KJ.08.09—2017 Nuclear Power Structural Materials Light Water Reactor Environmental Fatigue Design Model", ASME Boiler and Pressure Vessel Code Section III-2004, NUREG/CR-6909, "Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials", and JNES-SS-1005, "Environmental Fatigue Evaluation Method for Nuclear Power Plants" regarding the fitting method of average curves for nuclear power structural materials, the establishment of design curves, and the component flow of environmental fatigue design models. It was developed based on the environmental fatigue data of nuclear power structural materials accumulated by the Institute of Metal Research, Chinese Academy of Sciences. The specific technical content is described in Table 1. Materials include 19MnNiMo reactor pressure vessel low-alloy steel forgings with the following chemical composition: 0.2C, 1.41Mn, <0.005P, 0.002S, 0.16Si, 0.78Ni, 0.13Cr, 0.49Mo, <0.002V, Bal Fe, and a heat treatment state of as-supplied. 022Cr17Ni12Mo2N main pipe austenitic stainless steel forgings. The first material has the following chemical composition: 0.026C, 0.36Si, 1.41Mn, 0.016P, 0.004S, 17.05Cr, 12.45Ni, 2.25Mo, 0.02Co, 0.0009B, 0.072N, Bal Fe, and the second material has the following chemical composition: 16.96Cr, 13.07Ni, 2.23Mo, 0.014C, 0.29Si, 1.4Mn, 0.003S, 0.015P, 0.12N, Bal Fe, with a heat treatment state of as-supplied. 022Cr19Ni10 reactor internals austenitic

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