COMPARISON OF МАSTER CURVE WITH NORMATIVE METHOD OF ESTIMATING WWER-1000 REACTOR PRESSURE VESSEL METAL FRACTURE TOUGHNESS

被引:0
|
作者
Revka, V. M. [1 ]
Chyrko, L. I. [1 ]
机构
[1] Natl Acad Sci Ukraine, Inst Nucl Res, Kiev, Ukraine
关键词
WWER-1000 reactor pressure vessel; surveillance specimens; radiation embrittlement; critical brittleness temperature; fracture toughness; Master curve;
D O I
10.15407/jnpae2024.01.058
中图分类号
O57 [原子核物理学、高能物理学];
学科分类号
070202 ;
摘要
The paper considers the generalized temperature dependence of the stress intensity factor K JC 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 RT 0 temperature as a temperature index instead of T K for the normative fracture toughness curve of SOU NNEGC 177:2019 was considered.
引用
收藏
页码:58 / 65
页数:8
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