1. Void swelling in ferritic-martensitic steels under high dose ion irradiation: Exploring possible contributions to swelling resistance. (February 2016) Authors: Wang, Xu; Yan, Qingzhi; Was, Gary S.; Wang, Lumin Journal: Scripta materialia Issue: Volume 112(2016) Page Start: 9 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water. (15th August 2019) Authors: Hanbury, Rigel D.; Was, Gary S. Journal: Corrosion science Issue: Volume 157(2019) Page Start: 305 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. Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water. Issue 9 (16th March 2015) Authors: Wang, Peng; Was, Gary S. Journal: Journal of materials research Issue: Volume 30:Issue 9(2015) Page Start: 1335 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
6. The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment. (December 2019) Authors: Kuang, Wenjun; Hesterberg, Justin; Was, Gary S. Journal: Corrosion science Issue: Volume 161(2019) Page Start: Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
7. 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) ↗
8. 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) ↗
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. 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) ↗