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Kurt Terrani
Kurt Terrani
USNC
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Title
Cited by
Cited by
Year
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
10872014
Accident tolerant fuel cladding development: Promise, status, and challenges
KA Terrani
Journal of Nuclear Materials 501, 13-30, 2018
8242018
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
6262014
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
5262013
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
4842015
Material selection for accident tolerant fuel cladding
BA Pint, KA Terrani, Y Yamamoto, LL Snead
Metallurgical and Materials Transactions E 2, 190-196, 2015
3282015
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
2872014
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
2642012
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
2442015
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
2202012
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
2092016
Silicon carbide composite for light water reactor fuel assembly applications
K Yueh, KA Terrani
Journal of Nuclear Materials 448 (1-3), 380-388, 2014
1842014
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
PD Edmondson, SA Briggs, Y Yamamoto, RH Howard, K Sridharan, ...
Scripta Materialia 116, 112-116, 2016
1742016
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
1672012
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
1662017
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
1522013
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
1492014
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
1342017
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
1312015
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
1212016
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Articles 1–20