A new method for determining the threshold level of impact energy for reactor pressure vessel metal

被引:0
作者
Kotrechko, S. [1 ]
Soroka, K. [1 ]
Revka, V. [2 ]
机构
[1] NAS Ukraine, GV Kurdyumov Inst Met Phys, 36 Academician Vernadsky Blvd, UA-03142 Kyiv, Ukraine
[2] Inst Nucl Res, B 47 Nauky Ave, UA-03680 Kyiv, Ukraine
关键词
IRRADIATION;
D O I
10.1016/j.ijpvp.2025.105509
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This paper presents the results of validation of a novel approach for finding the threshold level of impact energy to estimate a ductile to brittle transition temperature for ferritic and ferritic-martensitic steels used for the manufacture of reactor pressure vessels (RPV). The idea of the proposed approach is that the value of the threshold level of impact energy is adjusted depending on the strength of the steel. The opportunity of increasing the threshold level of impact energy KVth as the strength of RPV steels increases is validated. The KVth correction technique is described using surveillance test data for Charpy impact and uniaxial tension tests. For highly embrittled RPV steels (transition temperature shift around 160 degrees C or more), the ASTM E185 standard method is shown to clearly underestimate the radiation shift as compared to a physically based approach.
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页数:8
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