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A study on the fatigue and fracture characteristics of localized nuclear reactor vessel material
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 Title & Authors
A study on the fatigue and fracture characteristics of localized nuclear reactor vessel material
Jeong, Sun-Eok;
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 Abstract
It is important to ensure the reliability of the first localized reactor vessel steel. To satisfy with this purpose, a study on the impact/hardness, low cycle fatigue(LCF), crack growth rate(da/dN) and fracture toughness( ) of base material(BM) and weld metal(WM) were performed under room temperature air and corrosion conditions. A summary of the results is as folows : (1) Charpy impact absorbed energy of BM was the highest value, heat affected zoon(HAZ) and the lowest, WM. The hardness of BM was similar to HAZ. (2) Coefficients of Manson equation using the monotonic tensile test data were obtained for the present material. (3) The effects of stress ratio and ambient (120.deg. C and NaCl) condition on da/dN were investigated, da/dN with NaCl condition expressed the highest value. (4) The results of Charpy V-notch impact test had good correlation with characteristics and the lowest curve of for BM was derived, more researches about WM and HAZ are required hereafter.
 Keywords
Low cycle Fatigue;Stress Intensity Factor;Crack Growth Rate;Heat Affected Zone;
 Language
Korean
 Cited by
1.
고온수중에서 STS 304 스테인리스강의 응력부식균열 성장속도,김정기;

대한기계학회논문집A, 2000. vol.24. 1, pp.156-162 crossref(new window)
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