Reference temperature determination of RPV steel using small-sized fracture toughness specimens

M. Zarazovskii , S. Shukayev , K. Lukianenko
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引用次数: 0

Abstract

The efficiency of the Master-Curve reference temperature (MCRT) determination for Reactor Pressure Vessel (RPV) material using three-point bending half-thick SE(B) and compact tension C(T)0.16T specimens is analysed. The designed and manufactured experimental equipment for fracture toughness (FT) testing at cryogenic temperatures is described. For specimen cooling the liquid nitrogen and its vapours were used. Specimen pre-cracking was performed according to ASTM E647 standard, FT testing, and data treatment – in accordance with ASTM E399 and ASTM E1921. The experiments were carried-out on the specimens produced from two WWER-1000 RPV forgings made of 15Kh2NMFAA steel in initial (unirradiated) state. The experimental data were processed using the Master Curve methodology. It is shown that the as old USSR’s PNAE G-7-002-86 design FT curve as well as modern Ukrainian SOU NAEK 177:2023 and EU’s VERLIFE curves, are too conservative relatively to the obtained Master Curves.
用小尺寸断裂韧性试样测定RPV钢的参考温度
分析了用三点弯曲半厚SE(B)和0.16T致密拉伸C(T)试样测定反应堆压力容器(RPV)材料主曲线参考温度(MCRT)的效率。介绍了自行设计制造的低温断裂韧性试验装置。试样的冷却采用液氮及其蒸气。试样预裂按照ASTM E647标准进行,FT测试和数据处理-按照ASTM E399和ASTM E1921。在初始(未辐照)状态下,对2个15Kh2NMFAA钢的wer -1000 RPV锻件进行了试验。实验数据采用主曲线法进行处理。结果表明,旧苏联的PNAE G-7-002-86设计的FT曲线以及现代乌克兰的SOU NAEK 177:2023和欧盟的VERLIFE曲线相对于得到的主曲线过于保守。
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CiteScore
1.70
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