Маster曲线与估算WWER-1000反应堆压力容器金属断裂韧性的规范方法的比较

IF 0.4 Q4 PHYSICS, NUCLEAR Nuclear Physics and Atomic Energy Pub Date : 2024-03-25 DOI:10.15407/jnpae2024.01.058
V. Revka, L. Chyrko
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引用次数: 0

摘要

本文考虑了 WWER-1000 反应堆压力容器金属应力强度因子 KJC 的广义温度依赖性,该因子是根据断裂韧性的监视测试数据推导出来的。研究了主曲线的形状和 95 % 置信上限和下限与裂纹抗力参数对温度的实验依赖性的一致性。从保守性和可接受性的角度出发,对 NPRR(《核电规则和条例》)G-7-002-86 和 SOU NNEGC(《乌克兰国家核能发电公司组织标准》)177:2019 规定的断裂韧性标准曲线与主曲线 5 % 置信度进行了比较。在 SOU NNEGC 177:2019 标准断裂韧性曲线中,考虑了使用 RT0 温度作为温度指数而不是 TK 的可能性。
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Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness
The paper considers the generalized temperature dependence of the stress intensity factor KJC in the WWER-1000 reactor pressure vessel metal, which was derived based on the surveillance test data for fracture toughness. The consistency of the shape of the Master curve and 95 % upper and lower confidence bounds with the experimental dependence of crack resistance parameters on temperature was studied. From the point of view of the level of conservatism and acceptability, a comparison of the normative curves of fracture toughness according to NPRR (Nuclear Power Rules and Regulations) G-7-002-86 and SOU NNEGC (Standard of organization of Ukraine, National Nuclear Energy Generating Company) 177:2019 with a 5 % confidence bound of the Master curve was carried out. The possibility of using RT0 temperature as a temperature index instead of TK for the normative fracture toughness curve of SOU NNEGC 177:2019 was considered.
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来源期刊
CiteScore
0.70
自引率
33.30%
发文量
10
审稿时长
19 weeks
期刊介绍: The journal Nuclear Physics and Atomic Energy presents the publications on Nuclear Physics, Atomic Energy, Radiation Physics, Radioecology, Engineering and Methods of Experiment. The journal includes peer-reviewed articles which are completed works containing new results of theoretical and experimental researches and are of interest for the scientists, postgraduate students, engineers and for the senior students.
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