EPRI activities to address reactor pressure vessel integrity issues von Rosinski, Stan T, Carter, Robert G

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Effect of Higher Strain Range Cycling on Near Fatigue-Limit Fatigue Life von Fukuoka, Chie, Nakagawa, Yukiya G., Rosinski, Stan T.

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Pressurized thermal shock screening criteria re-evaluation effort — US industry activities von Rosinski, Stan T, Hardies, Robert O

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Real-Time Optimization of the Mid-Columbia Hydropower System von Hamann, Andrew, Hug, Gabriela, Rosinski, Stan

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A Comparison of the tanh and Exponential Fitting Methods for Charpy V-Notch Energy Data von EricksonKirk, Marjorie Ann, EricksonKirk, Mark T, Rosinski, Stan, Spanner, Jack

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Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA von Server, William, Rosinski, Stan, Lott, Randy, Kim, Charles, Weakland, Dennis

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Effect of specimen size on the impact properties of neutron irradiated A533B steel von Schubert, L.E., Kumar, A.S., Rosinki, Stan T., Hamilton, Margaret L.

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Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA : Irradiation effect in reactor pressure vessel steels von SERVER, William, ROSINSKI, Stan, LOTT, Randy, KIM, Charles, WEAKLAND, Dennis

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Taking stock of component condition von VISWANATHAN, V, ROSINSKI, S, FOULD, J, WILLIAMS, J

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