| Accident tolerant fuels for LWRs: A perspective SJ Zinkle, KA Terrani, JC Gehin, LJ Ott, LL Snead Journal of Nuclear Materials 448 (1-3), 374-379, 2014 | 1150 | 2014 |
| Accident tolerant fuel cladding development: Promise, status, and challenges KA Terrani Journal of Nuclear Materials 501, 13-30, 2018 | 904 | 2018 |
| Advanced oxidation-resistant iron-based alloys for LWR fuel cladding KA Terrani, SJ Zinkle, LL Snead Journal of Nuclear Materials 448 (1-3), 420-435, 2014 | 657 | 2014 |
| High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments BA Pint, KA Terrani, MP Brady, T Cheng, JR Keiser Journal of nuclear materials 440 (1-3), 420-427, 2013 | 550 | 2013 |
| Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Y Yamamoto, BA Pint, KA Terrani, KG Field, Y Yang, LL Snead Journal of Nuclear Materials 467, 703-716, 2015 | 523 | 2015 |
| Material selection for accident tolerant fuel cladding BA Pint, KA Terrani, Y Yamamoto, LL Snead Metallurgical and Materials Transactions E 2, 190-196, 2015 | 343 | 2015 |
| Silicon carbide oxidation in steam up to 2 MPa KA Terrani, BA Pint, CM Parish, CM Silva, LL Snead, Y Katoh Journal of the American Ceramic Society 97 (8), 2331-2352, 2014 | 299 | 2014 |
| Microencapsulated fuel technology for commercial light water and advanced reactor application KA Terrani, LL Snead, JC Gehin Journal of Nuclear Materials 427 (1-3), 209-224, 2012 | 270 | 2012 |
| Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors NM George, K Terrani, J Powers, A Worrall, I Maldonado Annals of Nuclear Energy 75, 703-712, 2015 | 254 | 2015 |
| Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure T Cheng, JR Keiser, MP Brady, KA Terrani, BA Pint Journal of Nuclear Materials 427 (1-3), 396-400, 2012 | 231 | 2012 |
| Uniform corrosion of FeCrAl alloys in LWR coolant environments KA Terrani, BA Pint, YJ Kim, KA Unocic, Y Yang, CM Silva, HM Meyer III, ... Journal of Nuclear Materials 479, 36-47, 2016 | 226 | 2016 |
| Silicon carbide composite for light water reactor fuel assembly applications K Yueh, KA Terrani Journal of Nuclear Materials 448 (1-3), 380-388, 2014 | 198 | 2014 |
| Irradiation-enhanced α′ precipitation in model FeCrAl alloys PD Edmondson, SA Briggs, Y Yamamoto, RH Howard, K Sridharan, ... Scripta Materialia 116, 112-116, 2016 | 185 | 2016 |
| Fabrication and characterization of fully ceramic microencapsulated fuels KA Terrani, JO Kiggans, Y Katoh, K Shimoda, FC Montgomery, ... Journal of Nuclear Materials 426 (1-3), 268-276, 2012 | 173 | 2012 |
| A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys SA Briggs, PD Edmondson, KC Littrell, Y Yamamoto, RH Howard, ... Acta Materialia 129, 217-228, 2017 | 172 | 2017 |
| Protection of zirconium by alumina-and chromia-forming iron alloys under high-temperature steam exposure KA Terrani, CM Parish, D Shin, BA Pint Journal of Nuclear Materials 438 (1-3), 64-71, 2013 | 159 | 2013 |
| Thermo-mechanical analysis of LWR SiC/SiC composite cladding M Ben-Belgacem, V Richet, KA Terrani, Y Katoh, LL Snead Journal of nuclear materials 447 (1-3), 125-142, 2014 | 158 | 2014 |
| An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions KA Gamble, T Barani, D Pizzocri, JD Hales, KA Terrani, G Pastore Journal of nuclear materials 491, 55-66, 2017 | 147 | 2017 |
| Effect of steam on high temperature oxidation behaviour of alumina-forming alloys BA Pint, KA Unocic, KA Terrani Materials at High Temperatures 32 (1-2), 28-35, 2015 | 140 | 2015 |
| Rationalization of anisotropic mechanical properties of Al-6061 fabricated using ultrasonic additive manufacturing N Sridharan, M Gussev, R Seibert, C Parish, M Norfolk, K Terrani, ... Acta Materialia 117, 228-237, 2016 | 129 | 2016 |
Bruce A. PintConsultant, retired Oak Ridge National LaboratoryVerified email at ornl.gov
