Microstructural characterization of irradiation-induced Cu-enriched clusters in reactor pressure vessel steels von Carter, R.G., Soneda, N., Dohi, K., Hyde, J.M., English, C.A., Server, W.L.

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Application of the Master Curve in the ASME Code von Rosinski, S.T, Server, W.L

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An aging management approach for pressurized water reactor pressure vessels von Shah, V.N., Server, W.L.

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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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Adequacy of estimates and variability of fracture-related properties for reactor pressure vessel materials von Richardson, A.K., Server, W.L., Reuter, W.G.

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Leak-before-break: An integrated approach for high energy piping von Chexal, V.K., Norris, D.M., Server, W.L.

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The EPRI embrittlement management program von Griesbach, T.J., Server, W.L.

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The use of small specimen strength ratio for measuring fracture toughness von Server, W.L., Wullaert, R.A.

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Development of a statistical lower bound fracture toughness curve von Oldfield, W., Server, W.L., Wullaert, R.A., Stahlkopf, K.E.

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Thermal and structural analysis of light-water reactor vessel in-place annealing von Server, W.L., Houstrup, J.P.

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Integrity and Embrittlement Management of Reactor Pressure Vessels (RPVs) in Light-Water Reactors von Soneda Naoki

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Reactor Pressure Vessel (RPV) Design and Fabrication: The Case of the USA von Soneda Naoki

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Small specimen predictions of fracture toughness for nuclear pressure vessel steels von Wullaert, R.A., Server, W.L.

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Evaluating the Fracture Toughness of Reactor Pressure Vessel (RPV) Materials Subject to Embrittlement von Soneda Naoki

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A simple test method for measuring ?valid? JIc fracture toughness in Charpy-size surveillance specimens of nuclear pressure vessel steel von Ritchie, R. O., Server, W. L., Wullaert, R. A.

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An Aging Management Approach for Pressurized Water Reactor Pressure Vessels von Shah, V N, Server, W L

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Thermal and Structural Analysis of Light-Water Reactor Vessel In-Place Annealing von Server, W L, Houstrup, J P

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Leak-Before-Break: an Integrated Approach for High Energy Piping von Chexal, V K, Norris, D M, Server, W L

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Postirradiation annealing recovery of high copper reactor pressure vessel weld metal toughness properties / prepared by W.L. Server ; prepared for Division of Engineering Technolog... von Server, W. L

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Evaluation of system requirements and standards development for thermal annealing of reactor pressure vessels / prepared by W.L. Server von Server, W. L

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