☰

Kurt A. Terrani, Ph.D. - Publications

Affiliations: 
2010 Nuclear Engineering University of California, Berkeley, Berkeley, CA, United States 
Area:
Nuclear Engineering, Alternative Energy
Tree Info Similar researchers PubMed Report error

114 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2020 Lee SK, Liu M, Brown NR, Terrani KA, Lee Y. Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux Nuclear Technology. 206: 339-346. DOI: 10.1080/00295450.2019.1670010  0.33
2020 Capps N, Yan Y, Raftery A, Burns Z, Smith T, Terrani K, Yueh K, Bales M, Linton K. Integral LOCA fragmentation test on high-burnup fuel Nuclear Engineering and Design. 367: 110811. DOI: 10.1016/J.Nucengdes.2020.110811  0.369
2020 Capps N, Sweet R, Wirth BD, Nelson A, Terrani K. Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient Nuclear Engineering and Design. 366: 110744. DOI: 10.1016/J.Nucengdes.2020.110744  0.429
2020 Schappel D, Terrani K, Snead L, Wirth B. Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests Nuclear Engineering and Design. 357: 110428. DOI: 10.1016/J.Nucengdes.2019.110428  0.336
2020 Cakmak E, Gussev MN, Sridharan N, Seren MH, An K, Wang H, Terrani KA. Micromechanical and microstructure analysis of strain-induced phenomena in ultrasonic additively-manufactured Al-6061 alloy Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 770: 138533. DOI: 10.1016/J.Msea.2019.138533  0.321
2020 Hu X, Schappel D, Silva CM, Terrani KA. Fabrication of yttrium hydride for high-temperature moderator application Journal of Nuclear Materials. 539: 152335. DOI: 10.1016/J.Jnucmat.2020.152335  0.387
2020 Terrani KA, Capps NA, Kerr MJ, Back CA, Nelson AT, Wirth BD, Hayes SL, Stanek CR. Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing Journal of Nuclear Materials. 539: 152267. DOI: 10.1016/J.Jnucmat.2020.152267  0.37
2020 Sweet R, Yang Y, Terrani K, Wirth B, Nelson A. Performance of U3Si2 in an LWR following a cladding breach during normal operation Journal of Nuclear Materials. 539: 152263. DOI: 10.1016/J.Jnucmat.2020.152263  0.426
2020 Raiman SS, Field KG, Rebak RB, Yamamoto Y, Terrani KA. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding Journal of Nuclear Materials. 536: 152221. DOI: 10.1016/J.Jnucmat.2020.152221  0.371
2020 Massey CP, Edmondson PD, Unocic KA, Yang Y, Dryepondt SN, Kini A, Gault B, Terrani KA, Zinkle SJ. The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys Journal of Nuclear Materials. 533: 152105. DOI: 10.1016/J.Jnucmat.2020.152105  0.369
2020 McKinney C, Seibert R, Helmreich G, Aitkaliyeva A, Terrani K. Three-dimensional bubble reconstruction in high burnup UO2 Journal of Nuclear Materials. 532: 152053. DOI: 10.1016/J.Jnucmat.2020.152053  0.395
2020 Terrani KA, Jolly BC, Harp JM. Uranium nitride tristructural-isotropic fuel particle Journal of Nuclear Materials. 531: 152034. DOI: 10.1016/J.Jnucmat.2020.152034  0.369
2020 Schappel D, Brown NR, Terrani KA. Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON Journal of Nuclear Materials. 530: 151965. DOI: 10.1016/J.Jnucmat.2019.151965  0.32
2020 Hoelzer DT, Massey CP, Zinkle SJ, Crawford DC, Terrani KA. Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications Journal of Nuclear Materials. 529: 151928. DOI: 10.1016/J.Jnucmat.2019.151928  0.42
2020 Lee SK, Lee Y, Brown NR, Terrani KA. Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials International Journal of Heat and Mass Transfer. 158: 119970. DOI: 10.1016/J.Ijheatmasstransfer.2020.119970  0.331
2020 Burns JR, Hernandez R, Terrani KA, Nelson AT, Brown NR. Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5 Annals of Nuclear Energy. 142: 107423. DOI: 10.1016/J.Anucene.2020.107423  0.426
2020 Massey CP, Hoelzer DT, Unocic KA, Osetskiy YN, Edmondson PD, Gault B, Zinkle SJ, Terrani KA. Extensive Nanoprecipitate Morphology Transformation in a Nanostructured Ferritic Alloy due to Extreme Thermomechanical Processing Acta Materialia. DOI: 10.1016/J.Actamat.2020.09.020  0.319
2019 Raiman SS, Doyle P, Ang C, Katoh Y, Terrani KA. Hydrothermal Corrosion of Coatings on Silicon Carbide in Boiling Water Reactor Conditions Corrosion. 75: 217-223. DOI: 10.5006/2997  0.385
2019 Edmondson PD, Smith QB, Werden JW, Skiff D, Hobbs C, White JT, Dunwoody JT, Terrani KA, Nelson AT. Scanning Transmission Electron Microscopy Characterization of the Native Surfaces Oxides in High Density Ceramic Fuels Microscopy and Microanalysis. 25: 1594-1595. DOI: 10.1017/S1431927619008705  0.32
2019 Massey CP, Hoelzer DT, Edmondson PD, Kini A, Gault B, Terrani KA, Zinkle SJ. Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep Scripta Materialia. 170: 134-139. DOI: 10.1016/J.Scriptamat.2019.06.001  0.357
2019 Massey CP, Edmondson PD, Field KG, Hoelzer DT, Dryepondt SN, Terrani KA, Zinkle SJ. Post irradiation examination of nanoprecipitate stability and α′ precipitation in an oxide dispersion strengthened Fe-12Cr-5Al alloy Scripta Materialia. 162: 94-98. DOI: 10.1016/J.Scriptamat.2018.10.047  0.335
2019 Lu C, Koyanagi T, Katoh Y, Strydom G, Terrani KA, Brown NR. Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process Nuclear Engineering and Design. 345: 125-147. DOI: 10.1016/J.Nucengdes.2019.02.012  0.437
2019 Petrie CM, Burns JR, Raftery AM, Nelson AT, Terrani KA. Separate effects irradiation testing of miniature fuel specimens Journal of Nuclear Materials. 526: 151783. DOI: 10.1016/J.Jnucmat.2019.151783  0.396
2019 Singh G, Koyanagi T, Petrie C, Deck C, Terrani K, Arregui-Mena J, Katoh Y. Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopy Journal of Nuclear Materials. 523: 391-401. DOI: 10.1016/J.Jnucmat.2019.06.026  0.302
2019 Massey CP, Hoelzer DT, Seibert RL, Edmondson PD, Kini A, Gault B, Terrani KA, Zinkle SJ. Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration Journal of Nuclear Materials. 522: 111-122. DOI: 10.1016/J.Jnucmat.2019.05.019  0.381
2019 Koyanagi T, Terrani K, Karlsen T, Andersson V, Sprouster D, Ecker L, Katoh Y. In-pile tensile creep of chemical vapor deposited silicon carbide at 300 °C Journal of Nuclear Materials. 521: 63-70. DOI: 10.1016/J.Jnucmat.2019.04.048  0.333
2019 Finkeldei SC, Kiggans JO, Hunt RD, Nelson AT, Terrani KA. Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock Journal of Nuclear Materials. 520: 56-64. DOI: 10.1016/J.Jnucmat.2019.04.011  0.366
2019 McMurray JW, Hunt RD, Reif TJ, Helmreich GW, Silva CM, Seibert RL, Gerczak TJ, Terrani KA. Investigation of sol-gel feedstock additions and process variables on the density and microstructure of UN microspheres Journal of Nuclear Materials. 520: 78-86. DOI: 10.1016/J.Jnucmat.2019.04.003  0.333
2019 Seibert RL, Jolly BC, Balooch M, Schappel DP, Terrani KA. Production and characterization of TRISO fuel particles with multilayered SiC Journal of Nuclear Materials. 515: 215-226. DOI: 10.1016/J.Jnucmat.2018.12.024  0.342
2019 Singh G, Gorton J, Schappel D, Brown N, Katoh Y, Wirth B, Terrani K. Deformation analysis of SiC-SiC channel box for BWR applications Journal of Nuclear Materials. 513: 71-85. DOI: 10.1016/J.Jnucmat.2018.10.045  0.346
2019 Lee SK, Liu M, Brown NR, Terrani KA, Blandford ED, Ban H, Jensen CB, Lee Y. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel International Journal of Heat and Mass Transfer. 132: 643-654. DOI: 10.1016/J.Ijheatmasstransfer.2018.11.141  0.356
2019 George NM, Sweet RT, Powers JJ, Worrall A, Terrani KA, Wirth BD, Maldonado GI. Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors Annals of Nuclear Energy. 132: 486-503. DOI: 10.1016/J.Anucene.2019.04.025  0.44
2019 Cinbiz MN, Gussev M, Linton K, Terrani KA. An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading Annals of Nuclear Energy. 127: 30-38. DOI: 10.1016/J.Anucene.2018.11.051  0.337
2019 Massey CP, Dryepondt SN, Edmondson PD, Frith MG, Littrell KC, Kini A, Gault B, Terrani KA, Zinkle SJ. Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder Acta Materialia. 166: 1-17. DOI: 10.1016/J.Actamat.2018.11.062  0.386
2018 Gussev MN, Sridharan N, Thompson Z, Terrani KA, Babu SS. Influence of hot isostatic pressing on the performance of aluminum alloy fabricated by ultrasonic additive manufacturing Scripta Materialia. 145: 33-36. DOI: 10.1016/J.Scriptamat.2017.10.004  0.323
2018 Ali AF, Gorton JP, Brown NR, Terrani KA, Jensen CB, Lee Y, Blandford ED. Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys Nuclear Engineering and Design. 338: 218-231. DOI: 10.1016/J.Nucengdes.2018.08.024  0.352
2018 Schappel D, Terrani K, Powers J, Snead L, Wirth B. Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON Nuclear Engineering and Design. 335: 116-127. DOI: 10.1016/J.Nucengdes.2018.05.018  0.366
2018 Sweet R, George N, Maldonado G, Terrani K, Wirth B. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation Nuclear Engineering and Design. 328: 10-26. DOI: 10.1016/J.Nucengdes.2017.11.043  0.451
2018 Sridharan N, Gussev MN, Parish CM, Isheim D, Seidman DN, Terrani KA, Babu SS. Evaluation of microstructure stability at the interfaces of Al-6061 welds fabricated using ultrasonic additive manufacturing Materials Characterization. 139: 249-258. DOI: 10.1016/J.Matchar.2018.02.043  0.333
2018 Massey CP, Dryepondt SN, Edmondson PD, Terrani KA, Zinkle SJ. Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys Journal of Nuclear Materials. 512: 227-238. DOI: 10.1016/J.Jnucmat.2018.10.017  0.332
2018 Gerczak TJ, Parish CM, Edmondson PD, Baldwin CA, Terrani KA. Restructuring in high burnup UO2 studied using modern electron microscopy Journal of Nuclear Materials. 509: 245-259. DOI: 10.1016/J.Jnucmat.2018.05.077  0.359
2018 Terrani KA, Balooch M, Burns JR, Smith QB. Young's modulus evaluation of high burnup structure in UO2 with nanometer resolution Journal of Nuclear Materials. 508: 33-39. DOI: 10.1016/J.Jnucmat.2018.04.004  0.357
2018 Terrani KA. Accident tolerant fuel cladding development: Promise, status, and challenges Journal of Nuclear Materials. 501: 13-30. DOI: 10.1016/J.Jnucmat.2017.12.043  0.404
2018 Seibert RL, Terrani KA, Velázquez D, Hunn JD, Baldwin CA, Montgomery FC, Terry J. Local atomic structure of Pd and Ag in the SiC containment layer of TRISO fuel particles fissioned to 20% burn-up Journal of Nuclear Materials. 500: 316-326. DOI: 10.1016/J.Jnucmat.2017.12.032  0.38
2018 Terrani KA, Ang C, Snead LL, Katoh Y. Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa Journal of Nuclear Materials. 499: 242-247. DOI: 10.1016/J.Jnucmat.2017.11.040  0.305
2018 Singh G, Terrani K, Katoh Y. Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis Journal of Nuclear Materials. 499: 126-143. DOI: 10.1016/J.Jnucmat.2017.11.004  0.376
2018 Singh G, Sweet R, Brown N, Wirth B, Katoh Y, Terrani K. Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod Journal of Nuclear Materials. 499: 155-167. DOI: 10.1016/J.Jnucmat.2017.10.059  0.437
2018 Burns JR, Petrovic B, Chandler D, Terrani KA. Reactor physics phenomena in additively manufactured control elements for the High Flux Isotope Reactor Annals of Nuclear Energy. 115: 403-414. DOI: 10.1016/J.Anucene.2018.02.003  0.338
2018 Lu C, Hiscox BD, Terrani KA, Brown NR. Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics Annals of Nuclear Energy. 114: 277-287. DOI: 10.1016/J.Anucene.2017.12.021  0.454
2017 Rebak RB, Terrani KA, Gassmann WP, Williams JB, Ledford KL. Improving Nuclear Power Plant Safety with FeCrAl Alloy Fuel Cladding Mrs Advances. 2: 1217-1224. DOI: 10.1557/Adv.2017.5  0.414
2017 Fratoni M, Terrani KA. PWR core design with Metal Matrix Micro-encapsulated (M3) fuel Progress in Nuclear Energy. 100: 419-426. DOI: 10.1016/J.Pnucene.2017.07.009  0.397
2017 Gussev MN, Howard RH, Terrani KA, Field KG. Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing Nuclear Engineering and Design. 320: 298-308. DOI: 10.1016/J.Nucengdes.2017.06.008  0.372
2017 Gussev MN, Sridharan N, Norfolk M, Terrani KA, Babu SS. Effect of post weld heat treatment on the 6061 aluminum alloy produced by ultrasonic additive manufacturing Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 684: 606-616. DOI: 10.1016/J.Msea.2016.12.083  0.33
2017 McMurray J, Hu R, Ushakov S, Shin D, Pint B, Terrani K, Navrotsky A. Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels Journal of Nuclear Materials. 492: 128-133. DOI: 10.1016/J.Jnucmat.2017.05.016  0.341
2017 Petrie CM, Koyanagi T, McDuffee JL, Deck CP, Katoh Y, Terrani KA. Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux Journal of Nuclear Materials. 491: 94-104. DOI: 10.1016/J.Jnucmat.2017.04.058  0.364
2017 Gamble KA, Barani T, Pizzocri D, Hales JD, Terrani KA, Pastore G. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions Journal of Nuclear Materials. 491: 55-66. DOI: 10.1016/J.Jnucmat.2017.04.039  0.397
2017 Terrani K, Balooch M, Carpenter D, Kohse G, Keiser D, Meyer M, Olander D. Irradiation effects on thermal properties of LWR hydride fuel Journal of Nuclear Materials. 486: 381-390. DOI: 10.1016/J.Jnucmat.2017.01.030  0.628
2017 Balooch M, Olander DR, Terrani KA, Hosemann P, Casella AM, Senor DJ, Buck EC. Performance evaluation and post-irradiation examination of a novel LWR fuel composed of U 0.17 ZrH 1.6 fuel pellets bonded to Zircaloy-2 cladding by lead bismuth eutectic Journal of Nuclear Materials. 486: 391-401. DOI: 10.1016/J.Jnucmat.2016.08.020  0.61
2017 Parish CM, Terrani KA, Kim YJ, Koyanagi T, Katoh Y. Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments Journal of the European Ceramic Society. 37: 1261-1279. DOI: 10.1016/J.Jeurceramsoc.2016.11.033  0.377
2017 Cinbiz MN, Balooch M, Hu X, Amroussia A, Terrani K. Nanoindentation study of bulk zirconium hydrides at elevated temperatures Journal of Alloys and Compounds. 726: 41-48. DOI: 10.1016/J.Jallcom.2017.07.319  0.326
2017 Kabel J, Yang Y, Balooch M, Howard C, Koyanagi T, Terrani KA, Katoh Y, Hosemann P. Micro-mechanical evaluation of SiC-SiC composite interphase properties and debond mechanisms Composites Part B-Engineering. 131: 173-183. DOI: 10.1016/J.Compositesb.2017.07.035  0.362
2017 Liu M, Brown NR, Terrani KA, Ali AF, Blandford ED, Wachs DM. Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents Annals of Nuclear Energy. 110: 48-62. DOI: 10.1016/J.Anucene.2017.06.016  0.329
2017 Cinbiz MN, Brown NR, Terrani KA, Lowden RR, Erdman D. A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding Annals of Nuclear Energy. 109: 396-404. DOI: 10.1016/J.Anucene.2017.05.058  0.356
2017 Brown NR, Wysocki AJ, Terrani KA, Xu KG, Wachs DM. The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Annals of Nuclear Energy. 99: 353-365. DOI: 10.1016/J.Anucene.2016.09.033  0.423
2017 Briggs SA, Edmondson PD, Littrell KC, Yamamoto Y, Howard RH, Daily CR, Terrani KA, Sridharan K, Field KG. A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys ☆ Acta Materialia. 129: 217-228. DOI: 10.1016/J.Actamat.2017.02.077  0.365
2017 Frazer D, Szornel J, Krumwiede DL, Terrani KA, Hosemann P. Evaluation of the Mechanical Properties of TRISO Particles Using Nanoindentation and Ring Compression Testing Experimental Mechanics. 57: 1081-1090. DOI: 10.1007/S11340-017-0277-Z  0.316
2016 Parish CM, Gerczak TJ, Edmondson PD, Terrani KA. A Challenge to Multivariate Statistical Analysis: Spent Nuclear Fuel Microscopy and Microanalysis. 22: 330-331. DOI: 10.1017/S1431927616002506  0.342
2016 Edmondson PD, Briggs SA, Yamamoto Y, Howard RH, Sridharan K, Terrani KA, Field KG. Irradiation-enhanced α′ precipitation in model FeCrAl alloys Scripta Materialia. 116: 112-116. DOI: 10.1016/J.Scriptamat.2016.02.002  0.31
2016 Koyanagi T, Katoh Y, Terrani KA, Kim YJ, Kiggans JO, Hinoki T. Hydrothermal corrosion of silicon carbide joints without radiation Journal of Nuclear Materials. 481: 226-233. DOI: 10.1016/J.Jnucmat.2016.09.027  0.34
2016 Terrani KA, Pint BA, Kim YJ, Unocic KA, Yang Y, Silva CM, Meyer HM, Rebak RB. Uniform corrosion of FeCrAl alloys in LWR coolant environments Journal of Nuclear Materials. 479: 36-47. DOI: 10.1016/J.Jnucmat.2016.06.047  0.356
2016 Sooby Wood E, Terrani KA, Nelson AT. Sensitivity of measured steam oxidation kinetics to atmospheric control and impurities Journal of Nuclear Materials. 477: 228-233. DOI: 10.1016/J.Jnucmat.2016.05.023  0.322
2016 Massey CP, Terrani KA, Dryepondt SN, Pint BA. Cladding burst behavior of Fe-based alloys under LOCA Journal of Nuclear Materials. 470: 128-138. DOI: 10.1016/J.Jnucmat.2015.12.018  0.361
2016 Zinkle SJ, Terrani KA, Snead LL. Motivation for utilizing new high-performance advanced materials in nuclear energy systems Current Opinion in Solid State & Materials Science. 20: 401-410. DOI: 10.1016/J.Cossms.2016.10.004  0.328
2016 Sridharan N, Gussev M, Seibert R, Parish C, Norfolk M, Terrani K, Babu SS. Rationalization of anisotropic mechanical properties of Al-6061 fabricated using ultrasonic additive manufacturing Acta Materialia. 117: 228-237. DOI: 10.1016/J.Actamat.2016.06.048  0.338
2015 Silva CM, Snead LL, Hunn JD, Specht ED, Terrani KA, Katoh Y. Application of X-ray microcomputed tomography in the characterization of irradiated nuclear fuel and material specimens. Journal of Microscopy. 260: 163-74. PMID 26243381 DOI: 10.1111/Jmi.12279  0.369
2015 Silva CM, Hunt RD, Snead LL, Terrani KA. Synthesis of phase-pure U2N3 microspheres and its decomposition into UN. Inorganic Chemistry. 54: 293-8. PMID 25496440 DOI: 10.1021/Ic502457N  0.394
2015 Pint BA, Unocic KA, Terrani KA. Effect of steam on high temperature oxidation behaviour of alumina-forming alloys Energy Materials: Materials Science and Engineering For Energy Systems. 10: 28-35. DOI: 10.1179/0960340914Z.00000000058  0.389
2015 Yamamoto Y, Pint BA, Terrani KA, Field KG, Yang Y, Snead LL. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Journal of Nuclear Materials. 467: 703-716. DOI: 10.1016/J.Jnucmat.2015.10.019  0.429
2015 Gussev MN, Byun TS, Yamamoto Y, Maloy SA, Terrani KA. In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding Journal of Nuclear Materials. 466: 417-425. DOI: 10.1016/J.Jnucmat.2015.08.030  0.373
2015 Terrani KA, Yang Y, Kim YJ, Rebak R, Meyer HM, Gerczak TJ. Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation Journal of Nuclear Materials. 465: 488-498. DOI: 10.1016/J.Jnucmat.2015.06.019  0.365
2015 Hu X, Terrani KA, Wirth BD, Snead LL. Hydrogen permeation in FeCrAl alloys for LWR cladding application Journal of Nuclear Materials. 461: 282-291. DOI: 10.1016/J.Jnucmat.2015.02.040  0.462
2015 Terrani KA, Silva CM. High temperature steam oxidation of SiC coating layer of TRISO fuel particles Journal of Nuclear Materials. 460: 160-165. DOI: 10.1016/J.Jnucmat.2015.02.022  0.356
2015 Terrani KA, Kiggans JO, Silva CM, Shih C, Katoh Y, Snead LL. Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form Journal of Nuclear Materials. 457: 9-17. DOI: 10.1016/J.Jnucmat.2014.10.034  0.394
2015 George NM, Terrani K, Powers J, Worrall A, Maldonado I. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors Annals of Nuclear Energy. 75: 703-712. DOI: 10.1016/J.Anucene.2014.09.005  0.423
2015 Pint BA, Terrani KA, Yamamoto Y, Snead LL. Material selection for accident tolerant fuel cladding Metallurgical and Materials Transactions E. 2: 190-196. DOI: 10.1007/S40553-015-0056-7  0.384
2014 George NM, Maldonado I, Terrani K, Godfrey A, Gehin J, Powers J. Neutronics studies of uranium-bearing fully ceramic microencapsulated fuel for pressurized water reactors Nuclear Technology. 188: 238-251. DOI: 10.13182/Nt14-3  0.412
2014 Gentry C, Maldonado I, Godfrey A, Terrani K, Gehin J, Powers J. A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs Nuclear Technology. 186: 60-75. DOI: 10.13182/Nt13-75  0.366
2014 Terrani KA, Pint BA, Parish CM, Silva CM, Snead LL, Katoh Y. Silicon carbide oxidation in steam up to 2 MPa Journal of the American Ceramic Society. 97: 2331-2352. DOI: 10.1111/Jace.13094  0.351
2014 Hu X, Terrani KA, Wirth BD. Hydrogen desorption kinetics from zirconium hydride and zirconium metal in vacuum Journal of Nuclear Materials. 448: 87-95. DOI: 10.1016/J.Jnucmat.2014.01.028  0.335
2014 Ben-Belgacem M, Richet V, Terrani KA, Katoh Y, Snead LL. Thermo-mechanical analysis of LWR SiC/SiC composite cladding Journal of Nuclear Materials. 447: 125-142. DOI: 10.1016/J.Jnucmat.2014.01.006  0.406
2014 Farmer MT, Leibowitz L, Terrani KA, Robb KR. Scoping assessments of ATF impact on late-stage accident progression including molten core-concrete interaction Journal of Nuclear Materials. 448: 534-540. DOI: 10.1016/J.Jnucmat.2013.12.022  0.389
2014 Zinkle SJ, Terrani KA, Gehin JC, Ott LJ, Snead LL. Accident tolerant fuels for LWRs: A perspective Journal of Nuclear Materials. 448: 374-379. DOI: 10.1016/J.Jnucmat.2013.12.005  0.433
2014 Yueh K, Terrani KA. Silicon carbide composite for light water reactor fuel assembly applications Journal of Nuclear Materials. 448: 380-388. DOI: 10.1016/J.Jnucmat.2013.12.004  0.422
2014 Snead LL, Terrani KA, Katoh Y, Silva C, Leonard KJ, Perez-Bergquist AG. Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions Journal of Nuclear Materials. 448: 389-398. DOI: 10.1016/J.Jnucmat.2013.09.056  0.354
2014 Terrani KA, Wang D, Ott LJ, Montgomery RO. The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents Journal of Nuclear Materials. 448: 512-519. DOI: 10.1016/J.Jnucmat.2013.09.051  0.404
2014 Terrani KA, Zinkle SJ, Snead LL. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding Journal of Nuclear Materials. 448: 420-435. DOI: 10.1016/J.Jnucmat.2013.06.041  0.397
2014 Yan Y, Keiser JR, Terrani KA, Bell GL, Snead LL. Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions Journal of Nuclear Materials. 448: 436-440. DOI: 10.1016/J.Jnucmat.2013.05.071  0.374
2013 Hosemann P, Martos JN, Frazer D, Vasudevamurthy G, Byun TS, Hunn JD, Jolly BC, Terrani K, Okuniewski M. Mechanical characteristics of SiC coating layer in TRISO fuel particles Journal of Nuclear Materials. 442: 133-142. DOI: 10.1016/J.Jnucmat.2013.08.041  0.375
2013 Silva CM, Lindemer TB, Hunt RD, Collins JL, Terrani KA, Snead LL. Evaluation of sintering effects on SiC-incorporated UO2 kernels under Ar and Ar-4%H2 environments Journal of Nuclear Materials. 443: 596-602. DOI: 10.1016/J.Jnucmat.2013.08.007  0.37
2013 Pint BA, Terrani KA, Brady MP, Cheng T, Keiser JR. High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments Journal of Nuclear Materials. 440: 420-427. DOI: 10.1016/J.Jnucmat.2013.05.047  0.387
2013 Terrani KA, Parish CM, Shin D, Pint BA. Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure Journal of Nuclear Materials. 438: 64-71. DOI: 10.1016/J.Jnucmat.2013.03.006  0.387
2013 Terrani KA, Silva CM, Kiggans JO, Cai Z, Shin D, Snead LL. In situ ceramic layer growth on coated fuel particles dispersed in a zirconium metal matrix Journal of Nuclear Materials. 437: 171-177. DOI: 10.1016/J.Jnucmat.2013.02.042  0.322
2013 Shimoda K, Hinoki T, Terrani KA, Snead LL, Katoh Y. Processing of inert SiC matrix with triso coated fuel by liquid phase sintering Ceramic Engineering and Science Proceedings. 33: 25-31.  0.313
2012 Terrani KA, Snead LL, Gehin JC. Microencapsulated fuel technology for commercial light water and advanced reactor application Journal of Nuclear Materials. 427: 209-224. DOI: 10.1016/J.Jnucmat.2012.05.021  0.415
2012 Cheng T, Keiser JR, Brady MP, Terrani KA, Pint BA. Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure Journal of Nuclear Materials. 427: 396-400. DOI: 10.1016/J.Jnucmat.2012.05.007  0.402
2012 Terrani KA, Kiggans JO, Snead LL. Fabrication and preliminary evaluation of metal matrix microencapsulated fuels Journal of Nuclear Materials. 427: 79-86. DOI: 10.1016/J.Jnucmat.2012.04.010  0.357
2012 Terrani KA, Kiggans JO, Katoh Y, Shimoda K, Montgomery FC, Armstrong BL, Parish CM, Hinoki T, Hunn JD, Snead LL. Fabrication and characterization of fully ceramic microencapsulated fuels Journal of Nuclear Materials. 426: 268-276. DOI: 10.1016/J.Jnucmat.2012.03.049  0.43
2011 Terrani KA, Mamontov E, Balooch M, Olander DR. Incoherent quasielastic neutron scattering study of hydrogen diffusion in thorium-zirconium hydrides Journal of Nuclear Materials. 401: 91-97. DOI: 10.1016/J.Jnucmat.2010.04.003  0.556
2010 Terrani KA, Balooch M, Wongsawaeng D, Jaiyen S, Olander DR. The kinetics of hydrogen desorption from and adsorption on zirconium hydride Journal of Nuclear Materials. 397: 61-68. DOI: 10.1016/J.Jnucmat.2009.12.008  0.707
2010 Terrani KA, Balooch M, Siekhaus W, Olander DR. LWR hydride fuel rod irradiation Lwr Fuel Performance Meeting/Top Fuel/Wrfpm 2010. 794-798.  0.579
2009 Terrani KA, Chinthaka Silva GW, Yeamans CB, Balooch M, Olander DR. Fabrication and characterization of uranium-thorium-zirconium hydrides Journal of Nuclear Materials. 392: 151-157. DOI: 10.1016/J.Jnucmat.2009.03.031  0.677
2009 Terrani KA, Seifried JE, Olander DR. Transient hydride fuel behavior in LWRs Journal of Nuclear Materials. 392: 192-199. DOI: 10.1016/J.Jnucmat.2009.03.010  0.58
2008 Terrani KA. Transmission electron microscopy study of uranium thorium zirconium hydride fuels Microscopy and Microanalysis. 14: 658-659. DOI: 10.1017/S1431927608088648  0.313
2008 Terrani KA, Silva GWC, Yeamans CB. Fabrication and characterization of uranium thorium zirconium hydride fuels Transactions of the American Nuclear Society. 98: 1060-1061.  0.615
Show low-probability matches.