Fundamentals of Radiation Materials Science: Metals and Alloys von Was, Gary S

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Challenges to the use of ion irradiation for emulating reactor irradiation von Was, Gary S.

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Predicting structural material degradation in advanced nuclear reactors with ion irradiation von Taller, Stephen, VanCoevering, Gerrit, Wirth, Brian D., Was, Gary S.

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Emulation of fast reactor irradiated T91 using dual ion beam irradiation von Taller, Stephen, Jiao, Zhijie, Field, Kevin, Was, Gary S.

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The effect of cold rolling on grain boundary structure and stress corrosion cracking susceptibility of twins in alloy 690 in simulated PWR primary water environment von Kuang, Wenjun, Was, Gary S., Miller, Cody, Kaufman, Mike, Alam, Talukder, Gwalani, Bharat, Banerjee, Rajarshi

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Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water von Ampornrat, Pantip, Was, Gary S.

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The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel von Chen, Kai, Ickes, Michael R., Burke, Michael A., Was, Gary S.

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The influence of carbon on cavity evolution in ion-irradiated ferritic-martensitic steels von Monterrosa, Anthony M., Woodley, David, Jiao, Zhijie, Was, Gary S.

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Fundamentals of Radiation Materials Science: Metals and Alloys von WAS, GARY S

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The relationship between hardness and yield stress in irradiated austenitic and ferritic steels von Busby, Jeremy T., Hash, Mark C., Was, Gary S.

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Void swelling in high dose ion-irradiated reduced activation ferritic–martensitic steels von Wang, Xu, Monterrosa, Anthony M., Zhang, Feifei, Huang, Hao, Yan, Qingzhi, Jiao, Zhijie, Was, Gary S., Wang, Lumin

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The effect of grain boundary structure on the intergranular degradation behavior of solution annealed alloy 690 in high temperature, hydrogenated water von Kuang, Wenjun, Was, Gary S.

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Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments von Taller, Stephen, Was, Gary S.

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A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water von Kuang, Wenjun, Was, Gary S.

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Stress corrosion crack initiation in Alloy 690 in high temperature water von Moss, Tyler, Kuang, Wenjun, Was, Gary S

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Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water von Du, Donghai, Sun, Kai, Was, Gary S.

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A facility for studying irradiation accelerated corrosion in high temperature water von Raiman, Stephen S., Flick, Alexander, Toader, Ovidiu, Wang, Peng, Samad, Nassim A., Jiao, Zhijie, Was, Gary S.

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The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment von Kuang, Wenjun, Hesterberg, Justin, Was, Gary S.

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Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels von Song, Miao, Wang, Mi, Lou, Xiaoyuan, Rebak, Raul B., Was, Gary S.

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Reproducing shadow corrosion on Zircaloy-2 using in-situ proton irradiation von Wang, Peng, Nowotka, Karsten, Was, Gary S.

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