| Year |
Citation |
Score |
| 2023 |
Alam ME, Odette GR. Improving the Fracture Toughness and Ductility of Liquid-Phase Sintered WNiFe Tungsten Heavy Alloys by High-Temperature Annealing. Materials (Basel, Switzerland). 16. PMID 36769926 DOI: 10.3390/ma16030916 |
0.368 |
|
| 2020 |
Alam M, Odette G. On the remarkable fracture toughness of 90 to 97W-NiFe alloys revealing powerful new ductile phase toughening mechanisms Acta Materialia. 186: 324-340. DOI: 10.1016/j.actamat.2020.01.012 |
0.339 |
|
| 2020 |
Stan T, Wu Y, Ciston J, Yamamoto T, Odette GR. Characterization of polyhedral nano-oxides and helium bubbles in an annealed nanostructured ferritic alloy Acta Materialia. 183: 484-492. DOI: 10.1016/j.actamat.2019.10.045 |
0.308 |
|
| 2019 |
Bhattacharyya D, Yamamoto T, Wells P, Marquis E, Bachhav M, Wu Y, Davis J, Xu A, Odette GR. Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys Journal of Nuclear Materials. 519: 274-286. DOI: 10.1016/J.Jnucmat.2019.03.022 |
0.313 |
|
| 2019 |
Almirall N, Wells P, Yamamoto T, Wilford K, Williams T, Riddle N, Odette G. Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions Acta Materialia. 179: 119-128. DOI: 10.1016/J.ACTAMAT.2019.08.027 |
0.348 |
|
| 2018 |
Pal S, Alam M, Maloy S, Hoelzer D, Odette G. Texture evolution and microcracking mechanisms in as-extruded and cross-rolled conditions of a 14YWT nanostructured ferritic alloy Acta Materialia. 152: 338-357. DOI: 10.1016/j.actamat.2018.03.045 |
0.307 |
|
| 2018 |
Shu S, Wirth BD, Wells PB, Morgan DD, Odette GR. Multi-technique characterization of the precipitates in thermally aged and neutron irradiated Fe-Cu and Fe-Cu-Mn model alloys: Atom probe tomography reconstruction implications Acta Materialia. 146: 237-252. DOI: 10.1016/J.Actamat.2017.12.006 |
0.46 |
|
| 2017 |
Alam M, Pal S, Maloy S, Odette G. On delamination toughening of a 14YWT nanostructured ferritic alloy Acta Materialia. 136: 61-73. DOI: 10.1016/j.actamat.2017.06.041 |
0.369 |
|
| 2016 |
Alam M, Pal S, Fields K, Maloy S, Hoelzer D, Odette G. Tensile deformation and fracture properties of a 14YWT nanostructured ferritic alloy Materials Science and Engineering: A. 675: 437-448. DOI: 10.1016/j.msea.2016.08.051 |
0.394 |
|
| 2016 |
Cunningham NJ, Alinger MJ, Klingensmith D, Wu Y, Odette GR. On nano-oxide coarsening kinetics in the nanostructured ferritic alloy MA957: A mechanism based predictive model Materials Science and Engineering A. 655: 355-362. DOI: 10.1016/J.Msea.2015.12.074 |
0.788 |
|
| 2015 |
Maloy SA, Saleh TA, Anderoglu O, Romero TJ, Odette GR, Yamamoto T, Li S, Cole JI, Fielding R. Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ≈295°C to ≈6.5dpa Journal of Nuclear Materials. DOI: 10.1016/J.Jnucmat.2015.07.039 |
0.325 |
|
| 2015 |
Barnard L, Cunningham N, Odette GR, Szlufarska I, Morgan D. Thermodynamic and kinetic modeling of oxide precipitation in nanostructured ferritic alloys Acta Materialia. 91: 340-354. DOI: 10.1016/J.Actamat.2015.03.014 |
0.675 |
|
| 2014 |
Cunningham N, Wu Y, Klingensmith D, Odette GR. On the remarkable thermal stability of nanostructured ferritic alloys Materials Science and Engineering A. 613: 296-305. DOI: 10.1016/j.msea.2014.06.097 |
0.672 |
|
| 2014 |
Liu S, Odette GR, Segre CU. Evidence for core-Shell nanoclusters in oxygen dispersion strengthened steels measured using X-Ray absorption spectroscopy Journal of Nuclear Materials. 445: 50-56. DOI: 10.1016/J.Jnucmat.2013.10.042 |
0.35 |
|
| 2014 |
Cunningham NJ, Wu Y, Etienne A, Haney EM, Odette GR, Stergar E, Hoelzer DT, Kim YD, Wirth BD, Maloy SA. Effect of bulk oxygen on 14YWT nanostructured ferritic alloys Journal of Nuclear Materials. 444: 35-38. DOI: 10.1016/J.Jnucmat.2013.09.013 |
0.744 |
|
| 2012 |
Etienne A, Cunningham NJ, Wu Y, Odette GR. Effects of friction stir welding and post-weld annealing on nanostructured ferritic alloy Energy Materials: Materials Science and Engineering For Energy Systems. 6: 724-728. DOI: 10.1179/1743284710Y.0000000038 |
0.687 |
|
| 2012 |
Etienne A, Cunningham NJ, Wu Y, Odette GR. Effects of friction stir welding and post-weld annealing on nanostructured ferritic alloy Energy Materials: Materials Science and Engineering For Energy Systems. 6: 724-728. DOI: 10.1179/1743284710Y.0000000038 |
0.707 |
|
| 2012 |
Bhattacharyya D, Dickerson P, Odette GR, Maloy SA, Misra A, Nastasi MA. On the structure and chemistry of complex oxide nanofeatures in nanostructured ferritic alloy U14YWT Philosophical Magazine. 92: 2089-2107. DOI: 10.1080/14786435.2012.662760 |
0.301 |
|
| 2012 |
Wu Y, Haney EM, Cunningham NJ, Odette GR. Transmission electron microscopy characterization of the nanofeatures in nanostructured ferritic alloy MA957 Acta Materialia. 60: 3456-3468. DOI: 10.1016/J.Actamat.2012.03.012 |
0.671 |
|
| 2012 |
Dai Y, Odette GR, Yamamoto T. The effects of helium in irradiated structural alloys Comprehensive Nuclear Materials. 1: 141-193. DOI: 10.1016/B978-0-08-056033-5.00006-9 |
0.348 |
|
| 2011 |
Etienne A, Radiguet B, Cunningham NJ, Odette GR, Valiev R, Pareige P. Comparison of radiation-induced segregation in ultrafine-grained and conventional 316 austenitic stainless steels. Ultramicroscopy. 111: 659-63. PMID 21216102 DOI: 10.1016/J.Ultramic.2010.12.026 |
0.68 |
|
| 2011 |
Cunningham NJ, Etienne A, Odette GR, Stergar E, Wu Y, Wirth BD. Characterization of 14YWT as-atomized, milled, milled and annealed powders and HIP consolidated alloys Materials Research Society Symposium Proceedings. 1298: 3-8. DOI: 10.1557/Opl.2011.392 |
0.744 |
|
| 2011 |
Eiselt CC, Klimenkov M, Lindau R, Möslang A, Odette GR, Yamamoto T, Gragg D. Tensile and fracture toughness properties of the nanostructured oxide dispersion strengthened ferritic alloy 13Cr-1W-0.3Ti-0.3Y2O 3 Journal of Nuclear Materials. 417: 193-196. DOI: 10.1016/j.jnucmat.2010.12.066 |
0.389 |
|
| 2010 |
Odette G, Cunningham N, Yu Y, Etienne A, Haney E, Yamamoto T. Multiple Technique Characterization of a Nanostructured Ferritic Alloy: Heat-to-Heat, Long Term High Temperature Thermal Aging and Friction Stir Welding Effects on Nano-Scale Dispersion Strengthening Features Microscopy and Microanalysis. 16: 1600-1601. DOI: 10.1017/S1431927610062458 |
0.655 |
|
| 2010 |
Etienne A, Radiguet B, Cunningham NJ, Odette GR, Pareige P. Atomic scale investigation of radiation-induced segregation in austenitic stainless steels Journal of Nuclear Materials. 406: 244-250. DOI: 10.1016/J.Jnucmat.2010.08.043 |
0.656 |
|
| 2009 |
Jiang Y, Smith JR, Odette GR. Formation of Y-Ti-O nanoclusters in nanostructured ferritic alloys: A first-principles study Physical Review B - Condensed Matter and Materials Physics. 79. DOI: 10.1103/PhysRevB.79.064103 |
0.302 |
|
| 2009 |
Odette GR, Cunningham NJ, Marquis EA, Lozano-Perez S, De Castro V, Hosemann P, Stergar E, Liu S, Segre CU. Atom-probe tomography, small angle neutron scattering, transmission electron microscopy, positron annihilation spectroscopy and x-ray absorption spectroscopy characterization of nano-scale features in nanostructured ferritic alloys Microscopy and Microanalysis. 15: 244-245. DOI: 10.1017/S1431927609099553 |
0.643 |
|
| 2009 |
Alinger MJ, Glade SC, Wirth BD, Odette GR, Toyama T, Nagai Y, Hasegawa M. Positron annihilation characterization of nanostructured ferritic alloys Materials Science and Engineering A. 518: 150-157. DOI: 10.1016/J.Msea.2009.04.040 |
0.807 |
|
| 2009 |
Mueller P, Spätig P, Bonadé R, Odette GR, Gragg D. Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer97 Journal of Nuclear Materials. 386: 323-327. DOI: 10.1016/j.jnucmat.2008.12.122 |
0.303 |
|
| 2009 |
Alinger MJ, Odette GR, Hoelzer DT. On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys Acta Materialia. 57: 392-406. DOI: 10.1016/J.Actamat.2008.09.025 |
0.791 |
|
| 2008 |
Odette GR, Alinger MJ, Wirth BD. Recent developments in irradiation-resistant steels Annual Review of Materials Research. 38: 471-503. DOI: 10.1146/Annurev.Matsci.38.060407.130315 |
0.81 |
|
| 2008 |
Miao P, Odette GR, Yamamoto T, Alinger M, Klingensmith D. Thermal stability of nano-structured ferritic alloy Journal of Nuclear Materials. 377: 59-64. DOI: 10.1016/J.Jnucmat.2008.02.042 |
0.751 |
|
| 2008 |
Odette GR, Rathbun HJ, Hribernik M, Yamamoto T, He M, Spätig P. A multiscale approach to measuring and modeling cleavage fracture toughness in structural steels Nato Science For Peace and Security Series B: Physics and Biophysics. 203-226. DOI: 10.1007/978-1-4020-8422-5-10 |
0.748 |
|
| 2008 |
Miao P, Odette GR, Klingensmith D, Yamamoto T. On the thermal stability of 9% Cr tempered martensitic steels and nanostructured ferritic alloys Transactions of the American Nuclear Society. 98: 1150-1151. |
0.309 |
|
| 2008 |
Odette GR, Miao P, Yamamoto T, Edwards D, Tanagawa H, Kurtz R. A comparison of cavity formation in neutron irradiated nanostructured ferritic alloys and tempered martensitic steels at high He/dpa ratio Transactions of the American Nuclear Society. 98: 1148-1149. |
0.363 |
|
| 2008 |
Cunningham N, Odette GR. The effects of ball milling parameters on the homogeneity of Y-Ti-O nano-feature distribution in nano-structured ferritic alloys Transactions of the American Nuclear Society. 98: 1093-1094. |
0.68 |
|
| 2007 |
Miao P, Odette GR, Gould J, Bernath J, Miller R, Alinger M, Zanis C. The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding Journal of Nuclear Materials. 367: 1197-1202. DOI: 10.1016/J.Jnucmat.2007.03.232 |
0.764 |
|
| 2007 |
Yang WJ, Odette GR, Yamamoto T, Miao P, Alinger MJ, Hribernik M, Lee JH. A critical stress-critical area statistical model of the KJc (T) curve for MA957 in the cleavage transition Journal of Nuclear Materials. 367: 616-620. DOI: 10.1016/J.Jnucmat.2007.03.203 |
0.718 |
|
| 2007 |
Hoelzer DT, Bentley J, Sokolov MA, Miller MK, Odette GR, Alinger MJ. Influence of particle dispersions on the high-temperature strength of ferritic alloys Journal of Nuclear Materials. 367: 166-172. DOI: 10.1016/J.Jnucmat.2007.03.151 |
0.784 |
|
| 2007 |
Miao P, Odette GR, Yamamoto T, Alinger M, Hoelzer D, Gragg D. Effects of consolidation temperature, strength and microstructure on fracture toughness of nanostructured ferritic alloys Journal of Nuclear Materials. 367: 208-212. DOI: 10.1016/J.Jnucmat.2007.03.144 |
0.806 |
|
| 2007 |
Alinger MJ, Wirth BD, Lee HJ, Odette GR. Lattice Monte Carlo simulations of nanocluster formation in nanostructured ferritic alloys Journal of Nuclear Materials. 367: 153-159. DOI: 10.1016/J.Jnucmat.2007.03.010 |
0.785 |
|
| 2007 |
Monasterio PR, Wirth BD, Odette GR. Kinetic Monte Carlo modeling of cascade aging and damage accumulation in Fe-Cu alloys Journal of Nuclear Materials. 361: 127-140. DOI: 10.1016/j.jnucmat.2006.12.022 |
0.492 |
|
| 2006 |
Rathbun HJ, Odette GR, Yamamoto T, He MY, Lucas GE. Statistical and constraint loss size effects on cleavage fracture-implications to measuring toughness in the transition Journal of Pressure Vessel Technology, Transactions of the Asme. 128: 305-313. DOI: 10.1115/1.2217962 |
0.725 |
|
| 2006 |
Glade SC, Wirth BD, Odette GR, Asoka-Kumar P. Positron annihilation spectroscopy and small angle neutron scattering characterization of nanostructural features in high-nickel model reactor pressure vessel steels Journal of Nuclear Materials. 351: 197-208. DOI: 10.1016/J.Jnucmat.2006.02.012 |
0.521 |
|
| 2006 |
Rathbun HJ, Odette GR, He MY, Yamamoto T. Influence of statistical and constraint loss size effects on cleavage fracture toughness in the transition - A model based analysis Engineering Fracture Mechanics. 73: 2723-2747. DOI: 10.1016/j.engfracmech.2006.05.009 |
0.729 |
|
| 2006 |
Rathbun HJ, Odette GR, Yamamoto T, Lucas GE. Influence of statistical and constraint loss size effects on cleavage fracture toughness in the transition - A single variable experiment and database Engineering Fracture Mechanics. 73: 134-158. DOI: 10.1016/j.engfracmech.2005.07.008 |
0.721 |
|
| 2006 |
Odette GR, Yamamoto T, Miao P, Alinger MJ, Wirth BD, Hoelzer DT, Hashimoto N, Kurtz RJ, Gelles DS, Oliver BM. Development of nanostructured ferritic alloys for advanced fission and fusion energy applications Transactions of the American Nuclear Society. 94: 841-842. |
0.754 |
|
| 2005 |
Glade SC, Wirth BD, Odette GR, Asoka-Kumar P, Sterne PA, Howell RH. Positron annihilation spectroscopy and small-angle neutron scattering characterization of the effect of Mn on the nanostructural features formed in irradiated Fe-Cu-Mn alloys Philosophical Magazine. 85: 629-639. DOI: 10.1080/02678370412331320053 |
0.575 |
|
| 2004 |
Glade SC, Wirth BD, Asoka-Kumar P, Sterne PA, Odette GR. Positron annihilation spectroscopy of nanostructural features in model reactor pressure vessel steels Materials Science Forum. 445: 87-89. DOI: 10.4028/Www.Scientific.Net/Msf.445-446.87 |
0.541 |
|
| 2004 |
Kurtz RJ, Abe K, Chernov VM, Hoelzer DT, Matsui H, Muroga T, Odette GR. Recent progress on development of vanadium alloys for fusion Journal of Nuclear Materials. 329: 47-55. DOI: 10.1016/j.jnucmat.2004.04.299 |
0.321 |
|
| 2004 |
Wirth BD, Odette GR, Marian J, Ventelon L, Young-Vandersall JA, Zepeda-Ruiz LA. Multiscale modeling of radiation damage in Fe-based alloys in the fusion environment Journal of Nuclear Materials. 329: 103-111. DOI: 10.1016/j.jnucmat.2004.04.156 |
0.507 |
|
| 2004 |
Kishimoto H, Alinger MJ, Odette GR, Yamamoto T. TEM examination of microstructural evolution during processing of 14CrYWTi nanostructured ferritic alloys Journal of Nuclear Materials. 329: 369-371. DOI: 10.1016/J.Jnucmat.2004.04.044 |
0.784 |
|
| 2004 |
Alinger MJ, Odette GR, Hoelzer DT. The development and stability of Y-Ti-O nanoclusters in mechanically alloyed Fe-Cr based ferritic alloys Journal of Nuclear Materials. 329: 382-386. DOI: 10.1016/J.Jnucmat.2004.04.042 |
0.788 |
|
| 2004 |
Marian J, Wirth BD, Odette GR, Perlado JM. Cu diffusion in E-Fe: Determination of solute diffusivities using atomic-scale simulations Computational Materials Science. 31: 347-367. DOI: 10.1016/j.commatsci.2004.03.023 |
0.409 |
|
| 2003 |
Marian J, Wirth BD, Schäublin R, Odette GR, Perlado JM. MD modeling of defects in Fe and their interactions Journal of Nuclear Materials. 323: 181-191. DOI: 10.1016/j.jnucmat.2003.08.037 |
0.395 |
|
| 2003 |
Odette GR, Yamamoto T, Rathbun HJ, He MY, Hribernik ML, Rensman JW. Cleavage fracture and irradiation embrittlement of fusion reactor alloys: Mechanisms, multiscale models, toughness measurements and implications to structural integrity assessment Journal of Nuclear Materials. 323: 313-340. DOI: 10.1016/j.jnucmat.2003.08.023 |
0.769 |
|
| 2003 |
Miller MK, Wirth BD, Odette GR. Precipitation in neutron-irradiated Fe-Cu and Fe-Cu-Mn model alloys: A comparison of APT and SANS data Materials Science and Engineering A. 353: 133-139. |
0.466 |
|
| 2002 |
Asoka-Kumar P, Wirth BD, Sterne PA, Howell RH, Odette GR. Composition and magnetic character of nanometre-size Cu precipitates in reactor pressure vessel steels: Implications for nuclear power plant lifetime extension Philosophical Magazine Letters. 82: 609-615. DOI: 10.1080/0950083021000019958 |
0.428 |
|
| 2002 |
Asoka-Kumar P, Howell R, Nieh TG, Sterne PA, Wirth BD, Dauskardt RH, Flores KM, Suh D, Odette GR. Opportunities for materials characterization using high-energy positron beams Applied Surface Science. 194: 160-167. DOI: 10.1016/S0169-4332(02)00118-6 |
0.424 |
|
| 2002 |
Alinger MJ, Odette GR, Lucas GE. Tensile and fracture toughness properties of MA957: Implications to the development of nanocomposited ferritic alloys Journal of Nuclear Materials. 307: 484-489. DOI: 10.1016/S0022-3115(02)01220-5 |
0.809 |
|
| 2002 |
Odette GR, He M, Gragg D, Klingensmith D, Lucas GE. Some recent innovations in small specimen testing Journal of Nuclear Materials. 307: 1643-1648. DOI: 10.1016/S0022-3115(02)01173-X |
0.306 |
|
| 2002 |
Odette GR, Rathbun HJ, Rensman JW, Van den Broek FP. On the transition toughness of two RA martensitic steels in the irradiation hardening regime: A mechanism-based evaluation Journal of Nuclear Materials. 307: 1011-1015. DOI: 10.1016/S0022-3115(02)01166-2 |
0.712 |
|
| 2001 |
Wirth BD, Odette GR. Modeling Cascade Aging in Dilute Fe-Cu Alloys Mrs Proceedings. 701. DOI: 10.1557/PROC-701-T8.6.1 |
0.484 |
|
| 2001 |
Odette GR, Lucas GE, Klingensmith D. On the effect of neutron flux and composition on hardening of reactor pressure vessel steels and model alloys Materials Research Society Symposium - Proceedings. 650: R6.4.1-R6.4.6. DOI: 10.1557/Proc-650-R6.4 |
0.313 |
|
| 2001 |
Wirth BD, Asoka-Kumar P, Howell RH, Odette GR, Sterne PA. Positron annihilation spectroscopy and small angle neutron scattering characterization of nanostructural features in irradiated Fe-Cu-Mn alloys Materials Research Society Symposium - Proceedings. 650: R6.5.1-R6.5.6. |
0.483 |
|
| 2001 |
Wirth BD, Odette GR, Stoller RE. Recent progress toward an integrated multiscale-multiphysics model of reactor pressure vessel embrittlement Materials Research Society Symposium - Proceedings. 677: AA5.2.1-AA5.2.6. |
0.379 |
|
| 2001 |
Odette GR, Wirth BD, Bacon DJ, Ghoniem NM. Multiscale-multiphysics modeling of radiation-damaged materials: Embrittlement of pressure-vessel steels Mrs Bulletin. 26: 176-181. |
0.435 |
|
| 2001 |
Spätig P, Donahue E, Odette GR, Lucas GE, Victoria M. Transition regime fracture toughness-temperature properties of two advanced ferritic-martensitic steels Materials Research Society Symposium - Proceedings. 653: Z7.8.1-Z7.8.6. |
0.328 |
|
| 2000 |
Wirth BD, Odette GR, Maroudas D, Lucas GE. Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron Journal of Nuclear Materials. 276: 33-40. DOI: 10.1016/S0022-3115(99)00166-X |
0.406 |
|
| 2000 |
Donahue EG, Odette GR, Lucas GE. On the mechanisms and mechanics of fracture toughness of a V-4Cr-4Ti alloy Journal of Nuclear Materials. 283: 518-522. DOI: 10.1016/S0022-3115(00)00228-2 |
0.381 |
|
| 2000 |
Rathbun HJ, Odette GR, He MY. Size scaling of toughness in the transition: A single variable experiment and data base assessment American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) Pvp. 412: 113-118. |
0.691 |
|
| 1999 |
Wirth BD, Odette GR, Maroudas D, Lucas GE. Simulation of interstitial cluster mobility and cluster mediated surface topologies Materials Research Society Symposium - Proceedings. 504: 63-68. DOI: 10.1557/Proc-504-63 |
0.41 |
|
| 1999 |
Odette GR, Lucas GE, Klingensmith D. Anomalous hardening in model alloys and steels thermally aged at 290°C and 350°C: implications to low flux irradiation embrittlement Astm Special Technical Publication. 88-101. |
0.321 |
|
| 1999 |
Rathbun HJ, Odette GR, He MY, Lucas GE, Sheckherd JW. Statistical versus constraint size effects on the transition regime toughness: A preliminary study of a pressure vessel steel American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) Pvp. 393: 17-22. |
0.707 |
|
| 1998 |
Wirth BD, Odette GR. Kinetic Lattice Monte Carlo simulations of diffusion and decomposition kinetics in Fe-Cu alloys: Embedded atom and nearest neighbor potentials Materials Research Society Symposium - Proceedings. 481: 151-155. |
0.479 |
|
| 1997 |
Liu CL, Odette GR, Wirth BD, Lucas GE. A lattice Monte Carlo simulation of nanophase compositions and structures in irradiated pressure vessel Fe-Cu-Ni-Mn-Si steels Materials Science and Engineering A. 238: 202-209. DOI: 10.1016/S0921-5093(97)00450-4 |
0.311 |
|
| 1997 |
Wirth BD, Odette GR, Maroudas D, Lucas GE. Energetics of formation and migration of self-interstitials and self-interstitial clusters in α-iron Journal of Nuclear Materials. 244: 185-194. DOI: 10.1016/S0022-3115(96)00736-2 |
0.387 |
|
| 1997 |
Odette GR, Wirth BD. A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels Journal of Nuclear Materials. 251: 157-171. |
0.437 |
|
| 1997 |
Odette GR, Donahue E, Lucas GE. Cleavage mechanism in vanadium alloys Proceedings of the Tms Fall Meeting. 289. |
0.352 |
|
| 1997 |
Odette GR, Liu CL, Wirth BD. On the composition and structure of nanoprecipitates in irradiated pressure vessel steels Materials Research Society Symposium - Proceedings. 439: 457-469. |
0.448 |
|
| 1996 |
Odette GR, Lucas GE, Donahue E, Sheckherd JW. Fracture toughness and micromechanics in a V-4Cr-4Ti alloy Journal of Nuclear Materials. 233: 502-506. DOI: 10.1016/S0022-3115(96)00238-3 |
0.358 |
|
| 1996 |
Odette GR. Microstructural processes in structural alloys Journal of Computer-Aided Materials Design. 3: 15-24. DOI: 10.1007/BF01185631 |
0.341 |
|
| 1995 |
Alexander DE, Odette G, Lucas G, Rehn L. Electron Irradiation-Induced Mechanical Property Changes in Reactor Pressure Vessel Alloys Mrs Proceedings. 398. DOI: 10.1557/PROC-398-177 |
0.323 |
|
| 1991 |
Odette GR, Lucas GE. The effects of intermediate temperature irradiation on the mechanical behavior of 300-series austenitic stainless steels Journal of Nuclear Materials. 179: 572-576. DOI: 10.1016/0022-3115(91)90152-W |
0.364 |
|
| 1988 |
Lucas GE, Yih H, Odette GR. Analysis of cleavage fracture behavior in HT-9 with a statistical model Journal of Nuclear Materials. 155: 673-678. DOI: 10.1016/0022-3115(88)90393-5 |
0.35 |
|
| 1984 |
Odette GR, Lucas GE, Maiti R, Sheckherd JW. The mumechanical mechanisms of cleavage fracture in martensitic stainless steels Journal of Nuclear Materials. 122: 442-447. DOI: 10.1016/0022-3115(84)90637-8 |
0.327 |
|
| 1983 |
Odette GR, Lucas GE. Analysis of cleavage fracture potential of martensitic stainless steel fusion structures. Part II. Fracture analysis procedures for flawed fusion structures Journal of Nuclear Materials. 117: 276-286. DOI: 10.1016/0022-3115(83)90035-1 |
0.318 |
|
| 1983 |
Odette GR, Lucas GE. Analysis of cleavage fracture potential of martensitic stainless steel fusion structures. Part I. Micromechanical models and material properties Journal of Nuclear Materials. 117: 264-275. DOI: 10.1016/0022-3115(83)90034-X |
0.318 |
|
| 1981 |
Vagarali S, Odette G. A creep fracture model for irradiated and helium injected austenitic stainless steels Journal of Nuclear Materials. 104: 1239-1243. DOI: 10.1016/0022-3115(82)90771-1 |
0.317 |
|
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