Gary Was

Professor

gsw@umich.edu

1921 Cooley

T: (734) 763-4675

Bio

Projects

Publications

Facilities

Group


Publications

  1. Kuang, W and Was, GS (2020). A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary waterCORROSION SCIENCE, 163.

  2. Kuang, W and Was, GS (2020). The effect of grain boundary structure on the intergranular degradation behavior of solution annealed alloy 690 in high temperature, hydrogenated waterACTA MATERIALIA, 182:120-130.

  3. Kuhr, B, Farkas, D, Robertson, IM, Johnson, D, and Was, G (2020). Stress Localization Resulting from Grain Boundary Dislocation Interactions in Relaxed and Defective Grain BoundariesMETALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 51(2):667-683.

  4. Andresen, PL and Was, GS (2019). A historical perspective on understanding IASCCJOURNAL OF NUCLEAR MATERIALS, 517:380-392.

  5. Hanbury, RD and Was, GS (2019). Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature waterCORROSION SCIENCE, 157:305-311.

  6. Heidrich, B, Pimblott, SM, Was, GS, and Zinkle, S (2019). Roadmap for the application of ion beam technologies to the challenges of nuclear energy technologiesNUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 441:41-45.

  7. Hesterberg, J, Jiao, Z, and Was, GS (2019). Effects of post-irradiation annealing on the IASCC susceptibility of neutron-irradiated 304L stainless steelJOURNAL OF NUCLEAR MATERIALS, 526.

  8. Hesterberg, J, Smith, R, and Was, GS (2019). Atomistic simulation of the obstacle strengths of radiation-induced defects in an Fe-Ni-Cr austenitic stainless steelMODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING, 27(8).

  9. Jiao, Z, Hesterberg, J, and Was, GS (2019). Insights into the sources of irradiation hardening in a neutron irradiated 304L stainless steel following post-irradiation annealingJOURNAL OF NUCLEAR MATERIALS, 526.

  10. Johnson, DC, Kuhr, B, Farkas, D, and Was, GS (2019). Quantitative linkage between the stress at dislocation channel - Grain boundary interaction sites and irradiation assisted stress corrosion crack initiationACTA MATERIALIA, 170:166-175.

  11. Kuang, W, Hesterberg, J, and Was, GS (2019). The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environmentCORROSION SCIENCE, 161.

  12. Kubley, T, Naab, F, Toader, O, and Was, G (2019). Creation of a remotely monitored and controlled ion beam laboratory using novel hardware and software toolsNUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 438:31-37.

  13. Lear, CR, Song, M, Wang, M, and Was, GS (2019). Dual ion irradiation of commercial and advanced alloys: Evaluating microstructural resistance for high dose core internalsJOURNAL OF NUCLEAR MATERIALS, 516:125-134.

  14. Reyes, M, Wang, P, Was, G, and Marian, J (2019). Determination of dose rate effects on Zircaloy oxidation using proton irradiation and oxygen transport modelingJOURNAL OF NUCLEAR MATERIALS, 523:56-65.

  15. Song, M, Wang, M, Lou, X, Rebak, RB, and Was, GS (2019). Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels (vol 513, pg 33, 2019)JOURNAL OF NUCLEAR MATERIALS, 518:461.

  16. Song, M, Wang, M, Lou, X, Rebak, RB, and Was, GS (2019). Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steelsJOURNAL OF NUCLEAR MATERIALS, 513:33-44.

  17. Stoller, RE, Toloczko, MB, Was, GS, Certain, AG, Dwaraknath, S, and Garner, FA (2019). On the use of SRIM for computing radiation damage exposure (vol 310, pg 75, 2013)NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 459:196-197.

  18. Taller, S, Jiao, Z, Field, K, and Was, GS (2019). Emulation of fast reactor irradiated T91 using dual ion beam irradiationJOURNAL OF NUCLEAR MATERIALS, 527.

  19. Wang, M, Song, M, Lear, CR, and Was, GS (2019). Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internalsJOURNAL OF NUCLEAR MATERIALS, 515:52-70.

  20. Wang, M, Song, M, Was, GS, and Nelson, JL (2019). The roles of thermal mechanical treatment and delta phase in the stress corrosion cracking of alloy 718 in primary waterCORROSION SCIENCE, 160.

  21. Was, GS, Petti, D, Ukai, S, and Zinkle, S (2019). Materials for future nuclear energy systemsJOURNAL OF NUCLEAR MATERIALS, 527.

  22. Chen, Y, Dong, Y, Marquis, E, Jiao, Z, Hesterberg, J, Was, G, and Chou, P (2018). Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless SteelIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 973-991. Minerals Metals & Materials Series.

  23. Gussev, MN, Was, GS, Busby, JT, and Leonard, KJ (2018). Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic SteelsIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 1073-1084. Minerals Metals & Materials Series.

  24. Hanbury, RD and Was, GS (2018). Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary WaterIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 1087-1096. Minerals Metals & Materials Series.

  25. Hesterberg, JR, Jiao, Z, and Was, GS (2018). IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation AnnealingIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 1015-1026. Minerals Metals & Materials Series.

  26. Jiao, Z, Hesterberg, J, and Was, GS (2018). Effect of post-irradiation annealing on the irradiated microstructure of neutron-irradiated 304L stainless steelJOURNAL OF NUCLEAR MATERIALS, 500:220-234.

  27. Jiao, Z, Michalicka, J, and Was, GS (2018). Self-ion emulation of high dose neutron irradiated microstructure in stainless steelsJOURNAL OF NUCLEAR MATERIALS, 501:312-318.

  28. Jiao, Z, Taller, S, Field, K, Yeli, G, Moody, MP, and Was, GS (2018). Microstructure evolution of T91 irradiated in the BOR60 fast reactorJOURNAL OF NUCLEAR MATERIALS, 504:122-134.

  29. Johnson, DC and Was, GS (2018). Novel Technique for Quantitative Measurement of Localized Stresses Near Dislocation Channel-Grain Boundary Interaction Sites in Irradiated Stainless SteelIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 1005-1013. Minerals Metals & Materials Series.

  30. Kuang, W, Song, M, and Was, GS (2018). Insights into the stress corrosion cracking of solution annealed alloy 690 in simulated pressurized water reactor primary water under dynamic strainingACTA MATERIALIA, 151:321-333.

  31. Kuang, W, Was, GS, Miller, C, Kaufman, M, Alam, T, Gwalani, B, and Banerjee, R (2018). The effect of cold rolling on grain boundary structure and stress corrosion cracking susceptibility of twins in alloy 690 in simulated PWR primary water environmentCORROSION SCIENCE, 130:126-137.

  32. Mandapaka, KK and Was, GS (2018). Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature WaterIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 281-292. Minerals Metals & Materials Series.

  33. Mandapaka, KK, Cahyadi, RS, Yalisove, S, Kuang, W, Sickafus, K, Patel, MK, and Was, GS (2018). Corrosion behavior of ceramic-coated ZIRLO (TM) exposed to supercritical waterJOURNAL OF NUCLEAR MATERIALS, 498:495-504.

  34. Monterrosa, AM, Jiao, Z, and Was, GS (2018). The influence of helium on cavity evolution in ion-irradiated T91JOURNAL OF NUCLEAR MATERIALS, 509:707-721.

  35. Monterrosa, AM, Woodley, D, Jiao, Z, and Was, GS (2018). The influence of carbon on cavity evolution in ion-irradiated ferritic-martensitic steelsJOURNAL OF NUCLEAR MATERIALS, 509:722-735.

  36. Moss, T, Kuang, W, and Was, GS (2018). Stress corrosion crack initiation in Alloy 690 in high temperature waterCURRENT OPINION IN SOLID STATE & MATERIALS SCIENCE, 22(1):16-25.

  37. Park, D, Mouche, PA, Zhong, W, Mandapaka, KK, Was, GS, and Heuser, BJ (2018). TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposureJOURNAL OF NUCLEAR MATERIALS, 502:95-105.

  38. Song, M, Lear, CR, Parish, CM, Wang, M, and Was, GS (2018). Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterizationJOURNAL OF NUCLEAR MATERIALS, 510:396-413.

  39. Song, M, Wang, M, Was, GS, Nelson, L, and Pathania, R (2018). Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments-Part I: Microstructure CharacterizationIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 949-960. Minerals Metals & Materials Series.

  40. Song, M, Yang, Y, Wang, M, Kuang, W, Lear, CR, and Was, GS (2018). Probing long-range ordering in nickel-base alloys with proton irradiationACTA MATERIALIA, 156:446-462.

  41. Wang, M, Song, M, Was, GS, Nelson, L, and Pathania, R (2018). Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion CrackingIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 961-972. Minerals Metals & Materials Series.

  42. Wang, P and Was, GS (2018). In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary WaterIn: PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, ed. by Jackson, JH and Paraventi, D and Wright, M, pp. 245-258. Minerals Metals & Materials Series.

  43. Getto, E, Sun, K, and Was, GS (2017). Characterization of M2X formed during 5 MeV Fe2+ irradiationJOURNAL OF NUCLEAR MATERIALS, 485:154-158.

  44. Getto, E, Vancoevering, G, and Was, GS (2017). The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levelsJOURNAL OF NUCLEAR MATERIALS, 484:193-208.

  45. He, M, Johnson, DC, Was, GS, and Robertson, IM (2017). The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe-13Cr-15Ni alloyACTA MATERIALIA, 138:61-71.

  46. Judge, CD, Bhakhri, V, Jiao, Z, Klassen, RJ, Was, G, Botton, GA, and Griffiths, M (2017). The effects of proton irradiation on the microstructural and mechanical property evolution of inconel X-750 with high concentrations of heliumJOURNAL OF NUCLEAR MATERIALS, 492:213-226.

  47. Kuang, W, Song, M, Wang, P, and Was, GS (2017). The oxidation of alloy 690 in simulated pressurized water reactor primary waterCORROSION SCIENCE, 126:227-237.

  48. Moss, T and Was, GS (2017). Accelerated Stress Corrosion Crack Initiation of Alloys 600 and 690 in Hydrogenated Supercritical WaterMETALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 48A(4):1613-1628.

  49. Moss, T, Cao, G, and Was, GS (2017). Oxidation of Alloy 600 and Alloy 690: Experimentally Accelerated Study in Hydrogenated Supercritical WaterMETALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 48A(4):1596-1612.

  50. Raiman, SS and Was, GS (2017). Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature waterJOURNAL OF NUCLEAR MATERIALS, 493:207-218.

  51. Raiman, SS, Bartels, DM, and Was, GS (2017). Radiolysis driven changes to oxide stability during irradiation-corrosion of 316L stainless steel in high temperature waterJOURNAL OF NUCLEAR MATERIALS, 493:40-52.

  52. Silva, C, Song, M, Leonard, K, Wang, M, Was, G, and Busby, J (2017). Characterization of alloy 718 subjected to different thermomechanical treatmentsMATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 691:195-202.

  53. Taller, S, Woodley, D, Getto, E, Monterrosa, AM, Jiao, Z, Toader, O, Naab, F, Kubley, T, Dwaraknath, S, and Was, GS (2017). Multiple ion beam irradiation for the study of radiation damage in materialsNUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 412:1-10.

  54. Tan, L, Kim, BK, and Was, GS (2017). Evolution dependence of vanadium nitride nanoprecipitates on directionality of ion irradiationJOURNAL OF NUCLEAR MATERIALS, 495:425-430.

  55. Toader, O, Naab, F, Uberseder, E, Kubley, T, Taller, S, and Was, G (2017). Technical Aspects of Delivering Simultaneous Dual and Triple Ion Beams to a Target at the Michigan Ion Beam LaboratoryIn: CONFERENCE ON THE APPLICATION OF ACCELERATORS IN RESEARCH AND INDUSTRY (CAARI 2016), ed. by Parriott, C, vol. 90, pp. 385-390. Physics Procedia.

  56. Was, GS, Taller, S, Jiao, Z, Monterrosa, AM, Woodley, D, Jennings, D, Kubley, T, Naab, F, Toader, O, and Uberseder, E (2017). Resolution of the carbon contamination problem in ion irradiation experimentsNUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 412:58-65.

  57. Ahmedabadi, PM and Was, GS (2016). Stress Corrosion Cracking of Ferritic-Martensitic Steels in Simulated Boiling Water Reactor EnvironmentCORROSION, 72(1):66-77.

  58. Dwaraknath, SS and Was, GS (2016). The diffusion of cesium, strontium, and europium in silicon carbideJOURNAL OF NUCLEAR MATERIALS, 476:155-167.

  59. Dwaraknath, SS and Was, GS (2016). Radiation enhanced diffusion of cesium, strontium, and europium in silicon carbideJOURNAL OF NUCLEAR MATERIALS, 474:76-87.

  60. Getto, E, Sun, K, Monterrosa, AM, Jiao, Z, Hackett, MJ, and Was, GS (2016). Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steelsJOURNAL OF NUCLEAR MATERIALS, 480:159-176.

  61. Getto, E, Sun, K, Taller, S, Monterrosa, AM, Jiao, Z, and Was, GS (2016). Methodology for determining void swelling at very high damage under ion irradiationJOURNAL OF NUCLEAR MATERIALS, 477:273-279.

  62. Johnson, DC, Kuhr, B, Farkas, D, and Was, GS (2016). Quantitative analysis of localized stresses in irradiated stainless steels using high resolution electron backscatter diffraction and molecular dynamics modelingSCRIPTA MATERIALIA, 116:87-90.

  63. Roy, PK, Taller, S, Toader, O, Naab, F, Dwaraknath, S, and Was, GS (2016). A Multi-Pinhole Faraday Cup Device for Measurement of Discrete Charge Distribution of Heavy and Light IonsIEEE TRANSACTIONS ON NUCLEAR SCIENCE, 63(2, 2, SI):854-860.

  64. Song, M, Wen, J, Jiao, Z, and Was, GS (2016). Elastic strain energy control of the precipitate free zone around primary carbides in nickel base alloy 725ACTA MATERIALIA, 120:138-149.

  65. Stephenson, KJ and Was, GS (2016). The role of dislocation channeling in IASCC initiation of neutron irradiated stainless steelJOURNAL OF NUCLEAR MATERIALS, 481:214-225.

  66. Wang, X, Yan, Q, Was, GS, and Wang, L (2016). Void swelling in ferritic-martensitic steels under high dose ion irradiation: Exploring possible contributions to swelling resistanceSCRIPTA MATERIALIA, 112:9-14.

  67. Zhong, W, Mouche, PA, Han, X, Heuser, BJ, Mandapaka, KK, and Was, GS (2016). Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditionsJOURNAL OF NUCLEAR MATERIALS, 470:327-338.

  68. Allen, TR, Kaoumi, D, Wharry, JP, Jiao, Z, Topbasi, C, Kohnert, A, Barnard, L, Certain, A, Field, KG, Was, GS, Morgan, DL, Motta, AT, Wirth, BD, and Yang, Y (2015). Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperatureJOURNAL OF MATERIALS RESEARCH, 30(9):1246-1274.

  69. Getto, E, Jiao, Z, Monterrosa, AM, Sun, K, and Was, GS (2015). Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloysJOURNAL OF NUCLEAR MATERIALS, 465:116-126.

  70. Getto, E, Jiao, Z, Monterrosa, AM, Sun, K, and Was, GS (2015). Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9JOURNAL OF NUCLEAR MATERIALS, 462:458-469.

  71. Gulsoy, G and Was, GS (2015). Enhanced Oxygen Diffusion Within the Internal Oxidation Zone of Alloy 617 in Controlled Impurity Helium Environments from 1023 K to 1123 K (750 A degrees C to 850 A degrees C)METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 46A(4):1628-1638.

  72. Gulsoy, G and Was, GS (2015). Mechanism of Internal Oxidation of Alloy 617 in He-CO-CO2 Environments at 1123 K (850 degrees C)METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 46A(1):525-535.

  73. Gulsoy, G and Was, GS (2015). Surface oxidation of Alloy 617 in low oxygen partial pressure He-CO-CO2 environments at 750-850 degrees CCORROSION SCIENCE, 90:529-534.

  74. Kuang, W and Was, GS (2015). The effects of strain rate and carbon concentration on the dynamic strain aging of cold rolled Ni-based alloy in high temperature waterSCRIPTA MATERIALIA, 107:107-110.

  75. Kuang, W and Was, GS (2015). The effects of grain boundary carbide density and strain rate on the stress corrosion cracking behavior of cold rolled Alloy 690CORROSION SCIENCE, 97:107-114.

  76. Lupinacci, A, Chen, K, Li, Y, Kunz, M, Jiao, Z, Was, GS, Abad, MD, Minor, AM, and Hosemann, P (2015). Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffractionJOURNAL OF NUCLEAR MATERIALS, 458:70-76.

  77. McMurtrey, MD, Cui, B, Robertson, I, Farkas, D, and Was, GS (2015). Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steelCURRENT OPINION IN SOLID STATE & MATERIALS SCIENCE, 19(5):305-314.

  78. Moss, T and Was, GS (2015). Determination of the Nickel/Nickel Oxide Phase Transition and Henry's Constant in Hydrogenated Subcritical and Supercritical WaterJOURNAL OF THE ELECTROCHEMICAL SOCIETY, 162(1):C35-C41.

  79. Naab, FU, Toader, OF, and Was, GS (2015). Ion Beam Transport Simulations for the 1.7 MV Tandem Accelerator at the Michigan Ion Beam LaboratoryIn: 23rd International Conference on the Application of Accelerators in Research and Industry - CAARI 2014, ed. by Doyle, BL and Glass, GA and McDaniel, FD and Wang, Y and Parriott, CR, vol. 66, pp. 632-640. Physics Procedia.

  80. Stephenson, KJ and Was, GS (2015). Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protonsJOURNAL OF NUCLEAR MATERIALS, 456:85-98.

  81. Wang, P and Was, GS (2015). Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary waterJOURNAL OF MATERIALS RESEARCH, 30(9):1335-1348.

  82. Wang, X, Monterrosa, AM, Zhang, F, Huang, H, Yan, Q, Jiao, Z, Was, GS, and Wang, L (2015). Void swelling in high dose ion-irradiated reduced activation ferritic-martensitic steelsJOURNAL OF NUCLEAR MATERIALS, 462:119-125.

  83. Was, GS (2015). Challenges to the use of ion irradiation for emulating reactor irradiationJOURNAL OF MATERIALS RESEARCH, 30(9):1158-1182.

  84. Xu, C and Was, GS (2015). Proton irradiation creep of FM steel T91JOURNAL OF NUCLEAR MATERIALS, 459:183-193.

  85. Beckett, E, Hackett, M, Jiao, Z, Sun, K, and Was, GS (2014). MICROSTRUCTURAL EVOLUTION OF SELF-ION IRRADIATED HT9In: PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1.

  86. Campbell, AA and Was, GS (2014). Proton irradiation-induced creep of ultra-fine grain graphiteCARBON, 77:993-1010.

  87. Cui, B, Kacher, J, McMurtrey, M, Was, G, and Robertson, IM (2014). Influence of irradiation damage on slip transfer across grain boundariesACTA MATERIALIA, 65:150-160.

  88. Cui, B, McMurtrey, MD, Was, GS, and Robertson, IM (2014). Micromechanistic origin of irradiation-assisted stress corrosion crackingPHILOSOPHICAL MAGAZINE, 94(36):4197-4218.

  89. Dwaraknath, S and Was, GS (2014). Development of a multi-layer diffusion couple to study fission product transport in beta-SiCJOURNAL OF NUCLEAR MATERIALS, 444(1-3):170-174.

  90. Jiao, Z and Was, GS (2014). Precipitate behavior in self-ion irradiated stainless steels at high dosesJOURNAL OF NUCLEAR MATERIALS, 449(1-3):200-206.

  91. Jiao, Z, Was, G, Miura, T, and Fukuya, K (2014). Aspects of ion irradiations to study localized deformation in austenitic stainless steelsJOURNAL OF NUCLEAR MATERIALS, 452(1-3):328-334.

  92. McMurtrey, MD, Was, GS, Cui, B, Robertson, I, Smith, L, and Farkas, D (2014). Strain localization at dislocation channel-grain boundary intersections in irradiated stainless steelINTERNATIONAL JOURNAL OF PLASTICITY, 56:219-231.

  93. Raiman, SS, Flick, A, Toader, O, Wang, P, Samad, NA, Jiao, Z, and Was, GS (2014). A facility for studying irradiation accelerated corrosion in high temperature waterJOURNAL OF NUCLEAR MATERIALS, 451(1-3):40-47.

  94. Stephenson, KJ and Was, GS (2014). Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature waterJOURNAL OF NUCLEAR MATERIALS, 444(1-3):331-341.

  95. Was, GS and Andresen, PL (2014). Radiation damage to structural alloys in nuclear power plants: mechanisms and remediationIn: STRUCTURAL ALLOYS FOR POWER PLANTS: OPERATIONAL CHALLENGES AND HIGH-TEMPERATURE MATERIALS, ed. by Shirzadi, A and Jackson, S, pp. 355-420. Woodhead Publishing Series in Energy.

  96. Was, GS, Jiao, Z, Getto, E, Sun, K, Monterrosa, AM, Maloy, SA, Anderoglu, O, Sencer, BH, and Hackett, M (2014). Emulation of reactor irradiation damage using ion beams (vol 88, pg 33, 2014)SCRIPTA MATERIALIA, 93:60.

  97. Was, GS, Jiao, Z, Getto, E, Sun, K, Monterrosa, AM, Maloy, SA, Anderoglu, O, Sencer, BH, and Hackett, M (2014). Emulation of reactor irradiation damage using ion beamsSCRIPTA MATERIALIA, 88:33-36.

  98. Wharry, JP and Was, GS (2014). The mechanism of radiation-induced segregation in ferritic-martensitic alloysACTA MATERIALIA, 65:42-55.

  99. Xu, C and Was, GS (2014). Anisotropic dislocation loop distribution in alloy T91 during irradiation creepJOURNAL OF NUCLEAR MATERIALS, 454(1-3):255-264.

  100. Ashida, Y, Flick, A, Andresen, PL, and Was, GS (2013). Capabilities for Conducting Crack Growth Test of Neutron-Irradiated Alloys in Light Water Reactor EnvironmentsCORROSION, 69(2):136-144.