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Title: Effect of neutron irradiation and corrosive medium on the crack resistance of the water-moderated power reactor vessels

Journal Article · · Sov. At. Energy (Engl. Transl.); (United States)
DOI:https://doi.org/10.1007/BF01125198· OSTI ID:5102797

The authors conducted studies on vessel steel 15Kh2MFA and on two weld metals--steel 10KhMTF and an undesignated chromium-molybdenum steel--to determine their fracture properties under various neutron fluences and in corrosive coolant-simulating media consisting of distilled water and distilled water mixed with boric acid. The samples were irradiated in the VVR-M reactor of the Academy of Sciences of the USSR. Comparative test evaluations are graphed and analyzed.

OSTI ID:
5102797
Journal Information:
Sov. At. Energy (Engl. Transl.); (United States), Vol. 62:5; Other Information: Translated from At. Energ.; 62: No. 5, 348-350(May 1987)
Country of Publication:
United States
Language:
English

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