1. A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water. (1st May 2022) Authors: Kuang, Wenjun; Feng, Xingyu; Du, Donghai; Song, Miao; Wang, Mi; Was, Gary S. Journal: Corrosion science Issue: Volume 199(2022) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water. (February 2020) Authors: Kuang, Wenjun; Was, Gary S. Journal: Corrosion science Issue: Volume 163(2020) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
3. Challenges to the use of ion irradiation for emulating reactor irradiation. Issue 9 (13th April 2015) Authors: Was, Gary S. Journal: Journal of materials research Issue: Volume 30:Issue 9(2015) Page Start: 1158 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
4. Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature. Issue 9 (20th May 2015) Authors: Allen, Todd R.; Kaoumi, Djamel; Wharry, Janelle P.; Jiao, Zhijie; Topbasi, Cem; Kohnert, Aaron; Barnard, Leland; Certain, Alicia; Field, Kevin G.; Was, Gary S.; Morgan, Dane L.; Motta, Arthur T.; Wirth, Brian D.; Yang, Y. Journal: Journal of materials research Issue: Volume 30:Issue 9(2015) Page Start: 1246 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
5. Clarifying the mitigation effect of proton irradiation on the intergranular oxidation of 316L stainless steel in high temperature water. (December 2022) Authors: Wang, Shengkai; Zhang, Shihao; Xie, Jiayu; Feng, Xingyu; Song, Miao; Was, Gary S.; Kuang, Wenjun Journal: Acta materialia Issue: Volume 241(2022) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
6. Corrosion in Advanced Nuclear Reactors. (June 2021) Authors: Was, Gary S.; Allen, Todd R. Journal: Electrochemical Society Interface Issue: Volume 30:Number 2(2021) Page Start: 57 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
7. Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water. (December 2021) Authors: Du, Donghai; Sun, Kai; Was, Gary S. Journal: Corrosion science Issue: Volume 193(2021) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
8. Gary Was and Todd Allen Reply. (September 2020) Authors: Was, Gary S.; Allen, Todd R. Journal: New labor forum Issue: Volume 29:Number 3(2020) Page Start: 24 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
9. Insights into the roles of intergranular carbides in the initiation of intergranular stress corrosion cracking of alloy 690 in simulated PWR primary water. (March 2022) Authors: Kuang, Wenjun; Feng, Xingyu; Yue, Han; Was, Gary S.; Hao, Xianchao Journal: Corrosion science Issue: Volume 196(2022) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
10. Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic straining. (1st June 2018) Authors: Kuang, Wenjun; Song, Miao; Was, Gary S. Journal: Acta materialia Issue: Volume 151(2018) Page Start: 321 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗