Application of subsize specimens for re-irradiation embrittlement monitoring of the first generation of VVER-440 RPV steels

被引:0
作者
Russian Research Center, Kurchatov Institute, IRMT, Kur-chatov Sq. 1, 123182 Moscow, Russia [1 ]
机构
[1] Russian Research Center, Kurchatov Institute, IRMT, 123182 Moscow
来源
J. ASTM Int. | 2008年 / 7卷
关键词
Ductile-to-brittle transition temperature; Radiation embrittlement; Reactor pressure vessel; Specimen reconstitution; Subsize impact bend specimens;
D O I
10.1520/JAI101000
中图分类号
学科分类号
摘要
The first generation of WER-440 Units were not supplied with RPV steel surveillance programs. Therefore, cutting out of samples (templetes) from the inner side of RPV wall is the only possibility for re-irradiation embrittlement monitoring of the first generation of WER-440 RPV steels. Calculations showed that it is possible to cut out a sample of 7x60x95 mm (with consequent repair) from a RPV core weld. Thus, it is impossible to machine the standard 10x10x55 mm Charpy V-notch specimens to determine RPV steel radiation embrittlement. Therefore it is necessary to use subsize specimens (5x5x27.5 mm and 3x4x27 mm) for ductile-to-brittle transition temperature evaluation of templet material. The small samples were cut out from the inner surface of the all old Russian WER-440 RPVs to assess the actual condition of the RPV material before and after post-irradiation annealing and after re-irradiation. Special monitoring programs of periodic sampling of RPVs and re-irradiation of the templet material in surveillance channels of WER-440/213 RPVs were developed. The state of the art of application of subsize specimens for re-irradiation embrittlement monitoring of the first generation of WER-440 RPV steels is discussed. © 2008 by ASTM International.
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