@inbook{646bef8cc4e144f3ab3c748be887c4d0,
title = "Fatigue crack growth rates of irradiated pressure vessel steels in simulated nuclear coolant environment",
abstract = "The results of the first fatigue crack growth rate (FCGR) tests of irradiated pressure vessel steels in a simulated reactor coolant environment are presented. These results are compared with data on the same and similar unirradiated steels fatigue-tested in high-temperature air, and in high-temperature pressurized reactor-grade water. In the aqueous environment, irradiated condition test results show a slight increase in FCGR over those for unirradiated materials, while both classes of data show a substantial increase above FCGR data for the unirradiated condition in a high-temperature air environment. For unirradiated FCGR data, this increase has been attributed to a hydrogen-assistance model, and this is also suggested to be the case for the irradiated results. Possible interactions of material and environment, irradiation, damage, and hydrogen embrittlement effects are discussed.",
author = "William Cullen and Henry Watson and Robert Taylor and Kari T{\"o}rr{\"o}nen",
year = "1981",
doi = "10.1520/STP28209S",
language = "English",
isbn = "978-0-8031-0755-7",
series = "ASTM Special Technical Publication",
publisher = "American Society for Testing and Materials (ASTM)",
pages = "102--111",
editor = "David Kramer and H.R. Brager and J.S. Perrin",
booktitle = "Effects of Radiation on Materials",
address = "United States",
}