Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel

被引：0
|
作者：
J. Schuhknecht
U. Rindelhardt
H.-W. Viehrig
机构：
[1] Forschungszentrum Dresden-Rossendorf (FZD),
来源：
Strength of Materials | 2010年 / 42卷
关键词：
WWER-type reactors; reactor pressure vessel steel; weld metal; base metal; trepan; welding seam; fracture toughness; Master Curve; Charpy-V specimens;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
We present experimental results of the circumferential core weld SN0.1.4 and the base metal ring 0.3.1 of the reactor pressure vessel from the Unit 1 of the Greifswald WWER-440/230. The investigated trepans represent the irradiated–annealed– reirradiated (IAI) condition. The working program is focused on the characterization of the reactor pressure vessel steels through the reactor pressure vessel wall. The key part of the testing is aimed at the determination of the reference temperature T0 following the ASTM Test Standard E1921 to determine the fracture toughness in different thickness locations.
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页码：70 / 77
页数：7
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