Water corrosion of F82H-modified in simulated irradiation conditions by heat treatment

• Published in: Journal of nuclear materials Vol. 283; pp. 1341 - 1345
• Main Authors: Lapeña, J, Blázquez, F
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.12.2000
• Subjects: S06; T05; C08; H05
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/S0022-3115(00)00098-2

This paper presents results of testing carried out on F82H in water at 260°C with 2 ppm H 2 and the addition of 0.27 ppm Li in the form of LiOH. Uniform corrosion tests have been carried out on as-received material and on specimens from welded material [TIG and electron beam (EB)]. Stress corrosion cracking (SCC) tests have been carried out in as-received material and in material heat treated to simulate neutron irradiation hardening (1075°C/30′ a.c. and 1040°C/30′ + 625°C/1 h a.c.) with hardness values of 405 and 270 HV30, respectively. Results for uniform corrosion after 2573 h of testing have shown weight losses of about 60 mg/dm 2. Compact tension (CT) specimens from the as-received material tested under constant load have not experienced crack growth. However, in the simulated irradiation conditions for a stress intensity factor between 40 and 80 MPa√m, crack growth rates of about 7×10 −8 m/s have been measured.