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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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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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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The mechanism of radiation-induced segregation in ferritic–martensitic alloys von Wharry, Janelle P., 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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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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Celebrating the diamond anniversary of the Journal of Nuclear Materials von Was, Gary

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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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A systematic study of radiation-induced segregation in ferritic–martensitic alloys von Wharry, Janelle P., 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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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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A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water von Kuang, Wenjun, Feng, Xingyu, Du, Donghai, Song, Miao, Wang, Mi, Was, Gary S.

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Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials von Clowers, Logan N., 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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Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water von Wang, Peng, Grdanovska, Slavica, Bartels, David M., Was, Gary S.

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Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water von Hanbury, Rigel D., Was, Gary S.

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Insights into the roles of intergranular carbides in the initiation of intergranular stress corrosion cracking of alloy 690 in simulated PWR primary water von Kuang, Wenjun, Feng, Xingyu, Yue, Han, Was, Gary S., Hao, Xianchao

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