Curriculum Vitae: BRIAN D. WIRTH

Office:
4165 Etcheverry Hall
Department of Nuclear Engineering
Berkeley, CA 94720-1730
(510) 642-5341 (voice)
(510) 643-9685 (fax)
bdwirth@nuc.berkeley.edu


EDUCATION
University of California, Santa Barbara, Santa Barbara, CA.
PhD in Mechanical Engineering, Degree awarded: 12/1998
PhD Thesis Title: On The Character of Nano-scale Features in Reactor Pressure Vessel Steels Under Neutron Irradiation, Advisor: Professor G. Robert Odette
Georgia Institute of Technology, Atlanta, GA.
BS in Nuclear Engineering with Highest Honors, Degree awarded: 6/1992


PROFESSIONAL EXPERIENCE

7/2006 Associate Professor, Department of Nuclear Engineering, University of California, Berkeley
7/2002 - 6/2006 Assistant Professor, Department of Nuclear Engineering, University of California, Berkeley
2/2002 - 12/2002 Director, Chemistry and Materials Science Directorate Post-Doctoral Program, Chemistry and Materials Science Directorate, Lawrence Livermore National Laboratory
8/2000 - 12/2002 Staff member (indefinite career), Computational Materials Science Group, Materials Science and Technology Division, Chemistry and Materials Science Directorate, Lawrence Livermore National Laboratory
11/1998 - 8/2000 Staff member (flexible term appointment), Computational Materials Science Group, Materials Science and Technology Division, Chemistry and Materials Science Directorate, Lawrence Livermore National Laboratory
9/1998 - 11/1998 Research associate (development engineer), Department of Chemical Engineering, University of California, Santa Barbara
9/1992 - 9/1998 Graduate research associate, Departments of Chemical and Mechanical Engineering, University of California, Santa Barbara
6/1994 - 9/1994 Department of Energy, Nuclear Engineering Fellowship Research Practicuum, Oak Ridge National Laboratory, Small Angle Neutron Scattering and Atom Probe-Field Ion Microscope studies of Reactor Pressure Vessel Steels, Supervisor: Dr. R.K. Nanstad
6/1992 - 9/1992 Research associate, Kerforshungzentrum, Julich, Germany, Small Angle Neutron Scattering studies of Oxide Dispersion Strengthened Alloys, Supervisor: Dr. P. Krautwasser


HONORS AND AWARDS


REFEREED PUBLICATIONS:

Archival Journals

A50. J.-H. Shim, H.-J. Lee and B.D. Wirth, "Molecular dynamics simulation of primary irradiation defect formation in Fe-10%Cr" J. Nucl. Mater. 351 (2005) 56.

A49. L. Ventelon, B. Wirth and C. Domain, "Helium - self-interstitial atom interaction in alpha-iron" J. Nucl. Mater. 351 (2005) 119.

A48. S.C. Glade, B.D. Wirth, G.R. Odette, and P. Asoka-Kumar, "Positron annihilation spectroscopy and small angle neutron scattering characterization of nanostructural features in high-nickel model reactor pressure vessel steels" J. Nucl. Mater. 351 (2005) 197.

A47. J.S. Robach, I.M. Robertson, H.-J. Lee, and B.D. Wirth, "Dynamic observations and atomistic simulations of dislocation - defect interactions in rapidly quenched copper and gold" Acta. Mat. 54 (2006) 1679.

A46. I.M. Robertson, A. Beaudoin, K. Al-Fadhalah, Li. Chun-Ming, J. Robach, B.D. Wirth, A. Arsenlis, D. Ahn, and P. Sofronis, "Dislocation - obstacle interactions: dynamic experiments to continuum modeling" Materials Science and Engineering A 400-401 (2005) 245.

A45. B.-J. Lee, B.D. Wirth, J.-H. Shim, J. Kwon, S.C. Kwon, and J.-H. Hong, "Modified embedded-atom method interatomic potential for the Fe-Cu alloy system and cascade simulations on pure Fe and Fe-Cu alloys" Phys. Rev. B 71 (2005) 184205.

A44. L.A. Zepeda-Ruiz, J. Rottler, B.D. Wirth, R. Car, and D.J. Srolovitz, "Self-interstitial transport in vanadium" Acta. Mater 53 (2005) 1985.

A43. P. Jing, T. Khraishi, J.A. Young and B.D. Wirth "Multi-scale simulations of the effects of irradiation-induced voids and helium bubbles on the mechanical properties of aluminum" Phil. Mag. 85 (2005) 757.

A42. L. Zepeda-Ruiz, J. Marian and B.D. Wirth, "On the character of self-interstitial dislocation loops in vanadium" Phil. Mag. 85 (2005) 697.

A41. S.C. Glade, B.D. Wirth, G.R. Odette, P. Asoka-Kumar, P.A. Sterne, and R.H. Howell, "Positron annihilation spectroscopy and small angle neutron scattering characterizations of the effect of Mn on the nanostructural features formed in irradiated Fe-Cu-Mn alloys" Phil. Mag. 85 (2005) 629.

A40. J.A. Young and B.D. Wirth, "Dislocation motion and deformation at high strain rate in face-centered cubic metals" Phil. Mag. 84 (2004) 3755.

A39. A. Arsenlis, B.D. Wirth and M. Rhee, "Dislocation density-based constitutive model for the mechanical behavior of irradiated Cu" Phil. Mag. 84 (2004) 3617.

A38. J. Marian, B.D. Wirth, G.R. Odette, and J.M. Perlado, "Cu Diffusion in alpha-Fe: Determination of solute diffusivities using atomic-scale simulations" Comp. Mat. Sci. 31 (2004) 347.

A37. E.M. Bringa, J.U. Cazamias, P. Erhart, J. Stolken, N. Tanushev, B.D. Wirth, R.E. Rudd and M.J. Caturla, "Atomistic shock Hugoniot simulation of single-crystal copper", J. App. Phys. 96 (2004) 3793.

A36. B.D. Wirth, G.R. Odette, J. Marian, L. Ventelon, J.A. Young and L.A. Zepeda-Ruiz, "Multiscale Modeling of Radiation Damage in Fe-based Alloys in the Fusion Environment", J Nucl Mat 329-333 (2004) 103.

A35. B.D. Wirth and E.M. Bringa, "A Kinetic Monte Carlo Model for Helium Diffusion and Clustering in Fusion Environments", Physica Scripta T108 (2004) 80.

A34. S.C. Glade, B.D. Wirth, P. Asoka-Kumar, P.A. Sterne, and G.R. Odette, "Positron Annihilation Spectroscopy of Nanostructural Features in Model Reactor Pressure Vessel Steels", accepted for publication, Materials Science Forum, 445-446 (2004) 87.

A33. M.J. Fluss, B.D. Wirth, M. Wall, T.E. Felter, M.J. Caturla, A. Kubota, and T. Diaz de la Rubia, "Temperature dependent defect properties from ion irradiation in Pu(Ga)", Journal of Alloys and Compounds 368 (2004) 62.

A32. K. Morishita, R. Sugano and B.D. Wirth, "MD and KMC modeling of the growth and shrinkage mechanisms of helium-vacancy clusters in Fe", J Nucl Mat 323 (2003) 243.

A31. J. Marian, B.D. Wirth, R. Scaueblin, G.R. Odette and J.M. Perlado, "MD modeling of defects in Fe and their interactions", J Nucl Mat 323(2003) 181.

A30. K. Morishita, R. Sugano and B.D. Wirth, "Thermal stability of helium-vacancy clusters and bubble formation - Multiscale modeling for fusion materials development", Fusion Science and Technology 44 (2003) 441.

A29. J. Lerma, T. Khraishi, Y.L. Shen and B.D. Wirth, "The elastic fields of misfit cylindrical particles: a dislocation-based numerical approach", Mech. Res. Comm. 30 (2003) 325.

A28. M.K. Miller, B.D. Wirth and G.R. Odette, "Precipitation in Neutron Irradiated Fe-Cu and Fe-Cu-Mn Model Alloys: A Comparison of APT and SANS Data", Materials Science & Engineering A 353 (2003) 133.

A27. L.A. Zepeda-Ruiz, S. Han, D.J. Srolovitz, R. Car and B.D. Wirth, "Molecular dynamics study of the threshold displacement energy in vanadium", Phys Rev B 67 (2003) 134114.

A26. E.M. Bringa, B.D. Wirth, M.J. Caturla, J. Stolken, and D. Kalantar, "Materials far from equilibrium: from shocks to radiation damage", Nuclear Instruments and Methods B 202 (2003) 56.

A25. K. Morishita, R. Sugano, B.D. Wirth and T. Diaz de la Rubia, "Thermal stability of helium-vacancy clusters in iron", Nuclear Instruments and Methods B 202 (2003) 76.

A24. J.S. Robach, I.M. Robertson, B.D. Wirth, and A. Arsenlis, "In-situ transmission electron microscopy observations and molecular dynamics simulations of dislocation-defect interactions in ion-irradiated copper", Philosophical Magazine A 83 (2003) 955.

A23. J.M. Perlado, E. Dominguez, D. Lodi, J. Marian, M. Salvador, J. Sanz, A.I. Gonzalez, M.J. Caturla, T.D. De La Rubia, B.D. Wirth, and L. Colombo, "Insight into the Materials Choice for Inertial Fusion Energy Reactors Considering Radiation Damage: Neutron Irradiation Intensities and Basic Knowledge from Multiscale Modeling", Laser and Particle Beams 20 (2002) 627.

A22. A. Kimura, R. Kasada, K. Morishita, R. Sugano, A. Hasegawa, K. Abe, T. Yamamoto, H. Matsui, N. Yoshida, B.D. Wirth, and T. Diaz de la Rubia, "High Resistance to Helium Embrittlement in Reduced Activation Martensitic Steels", Journal of Nuclear Materials 307-311 (2002) 521.

A21. Y. Osetsky, D.J. Bacon, B.N. Singh and B. Wirth, "Atomistic Study of the Generation, Interaction, Accumulation and Annihilation of Cascade-Induced Defect Clusters", Journal of Nuclear Materials 307-311 (2002) 852.

A20. J. Marian, B.D. Wirth, R. Schaublin, J.M. Perlado, T. Diaz de la Rubia, "<100>-Loop characterization in a-Fe: comparison between experiments and modeling", Journal of Nuclear Materials 307-311 (2002) 871.

A19. R. Schaeublin, M.-J. Caturla, M. Wall, T. Felter, M. Fluss, B.D. Wirth, T. Diaz de la Rubia, and M. Victoria, "Correlating TEM images of damage in irradiated materials to molecular dynamics simulations", Journal of Nuclear Materials 307-311 (2002) 988.

A18. P. Asoka-Kumar, B.D. Wirth, P.A. Sterne, R.H. Howell, and G.R. Odette, "Composition and magnetic character of nanometer-size Cu precipitates in reactor pressure vessel steels: implications for nuclear power plant lifetime extension", Philosophical Magazine Letters 82 (2002) 609.

A17. M. Hiratani, H.M. Zbib and B.D. Wirth, "Interaction of glissile dislocations with perfect and truncated stacking-fault tetrahedra in irradiated metals", Philosophical Magazine A 82 (2002) 2709.

A16. P. Asoka-Kumar, R. Howell, T.G. Nieh, P.A. Sterne, B.D. Wirth, R.H. Dauskardt, K.M. Flores, D. Suh, G.R. Odette, "Opportunities for materials characterization using high-energy positron beams", Applied Surface Science 194 (2002) 160.

A15. J. Marian, B.D. Wirth and J.M. Perlado, "On the Mechanism of Formation and Growth of <100> Interstitial Loops in Ferritic Materials", Physical Review Letters 88 (2002) 255507.

A14. B.D. Wirth, V.V. Bulatov and T. Diaz de la Rubia, "Dislocation - Stacking Fault Tetrahedron Interactions in Cu", Journal of Engineering Materials and Technology 124 (2002) 329.

A13. S. Jumel, C. Domain, J. Ruste, J.-C. Van Duysen, C. Becquart, A. Legris, P. Pareige, A. Barbu, E. Van Walle, R. Chaouadi, M. Hou, G.R. Odette, R.E. Stoller, and B.D. Wirth, "Simulation of Irradiation Effects in Reactor Pressure Vessel Steels: the Reactor for Virtual Experiments (REVE) Project", Journal of Testing and Evaluation, 30 (2002) 37.

A12. J. Marian, B.D. Wirth, A. Caro, B. Sadigh, G.R. Odette, J.M. Perlado, and T. Diaz de la Rubia, "Dynamics of Self-Interstitial Cluster Migration in pure a-Fe and Fe-Cu Alloys", Physical Review B 65 (2002) 144102.

A11. J. Marian, B.D. Wirth, J.M. Perlado, G.R. Odette, and T. Diaz de la Rubia, "Dynamics of self-interstitial migration in Fe-Cu alloys", Physical Review B, 64 (2001) 094303/1.

A10. B. D. Wirth, M. J. Caturla, T. Diaz de la Rubia, T. Khraishi and H. Zbib, "Mechanical Property Degradation in Irradiated Materials: A Multiscale Modeling Approach", Nuclear Instruments and Methods B 180 (2001) 23.

A9. T. Diaz de la Rubia, H.M. Zbib, T.A. Khraishi, B.D. Wirth, M. Victoria and M.J. Caturla, "Plastic Flow Localization in Irradiated Materials: A Multiscale Modeling Approach", Nature 406 (2000) 871.

A8. B.D. Wirth, V. Bulatov and T. Diaz de la Rubia, "Atomistic Simulation of Stacking Fault Tetrahedra Formation in Cu", J. Nuc. Mat 283-287 (2000) 773.

A7. B.D. Wirth, G.R. Odette, D. Maroudas and G.E. Lucas, "Dislocation Loop Structure, Energy and Mobility of Self-Interstitial Clusters in BCC Iron", J. Nuc. Mat 276 (2000) 33.

A6. M.J. Caturla, N. Soneda, E. Alonso, B.D. Wirth, T. Diaz de la Rubia and J.M. Perlado, "Comparative study of radiation damage accumulation in Cu and Fe", J. Nuc. Mat 276 (2000) 13.

A5. G.R. Odette and B.D. Wirth, "A Computational Microscopy Study of Nanostructural Evolution in Irradiated Pressure Vessel Steels", J. Nuc. Mat 251 (1997) 157.

A4. R.E. Stoller, G.R. Odette, and B.D. Wirth, "Primary Damage Formation in BCC Iron", J. Nuc. Mat 251 (1997) 49.

A3. C.-L. Liu, G.R. Odette, B.D. Wirth, and G.E. Lucas, "A LMC Simulation of Nanophase Compositions and Structures in Irradiated Pressure Vessel Fe-Cu-Ni-Mn-Si Steels", Materials Science & Engineering A 238 (1997) 202.

A2. B.D. Wirth, G.R. Odette, D. Maroudas, and G.E. Lucas, "Energetics of Formation and Migration of Self-Interstitials and Self-Interstitial Clusters in a-Iron", J. Nuc. Mat 244 (1997) 185.

A1. P. Krautwasser, M. Widera, D. Esser, B.D. Wirth, et al.,"Thermal stability of dispersoids in the ferritic ODS alloys PM2000 and MA956", High Temperatures - High Pressures, 26 (no. 5) 1994, 549.


Conference and Symposium Proceedings

C24. R.E. Stoller, M.K. Miller, G.R. Odette, and B.D. Wirth, "Contributions of fundamental studies to understanding RPV embrittlement", Transactions of the American Nuclear Society, 88 (2003) 539.

C23. J.A. Young, B.D. Wirth, J. Robach and I. Robertson, "The interaction of dislocations and radiation-induced obstacles at high-strain rate", accepted for publication, 13th APS Topical Conference on Shock Compression of Condensed Matter, (2003)

C22. I.M. Robertson, J. Robach, B. Wirth and A. Arsenlis, "Dislocation behavior during deformation - combining experiments, simulation and modeling", MRS Soc. Symp. Proc 779 (2003) W.1.5.

C21. R. Daum, T. Allen, J. Cole, H. Tsai, D. Porter, B. Wirth and P. Spatig, "Plastic flow and fracture of cold-worked 316 stainless steel", Transactions of the American Nuclear Society, 87 (2002) 301.

C20. B.D. Wirth and G.R. Odette, "Recent progress towards a mechanistic model of reactor pressure vessel embrittlement", Proceedings of the International Symposium on the Mechanisms of Material Degradation and Non-Destructive Evaluation in Light Water Reactors, Institute of Nuclear Systems Safety, Osaka, Japan (2002) 77.

C19. J. Marian, B.D. Wirth, R. Schaublin and J.M. Perlado, "<100> dislocation loop formation and characterization in Ferritic Materials: Comparison between experiments and modeling", MRS Soc. Symp. Proc 731 (2002) W.1.4.

C18. I.M. Robertson, J. Robach, B. Wirth, "Mechanical properties of irradiated materials", Proceedings of International Conference on Nuclear Energy in Central Europe 2001, Ljubljana, Slovenia, Nuclear Society of Slovenia (2002) 3.

C17. B.D. Wirth, G.R. Odette, P. Asoka-Kumar, R.H. Howell, and P.A. Sterne, "Characterization of Nanostructural Features in Irradiated Reactor Pressure Vessel Model Alloys", Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Light Water Reactors, Ed., G.S. Was, National Association of Corrosion Engineers, 2002.

C16. K. Morishita, B.D. Wirth, T. Diaz de la Rubia, and A. Kimura, "Effects of Helium on Radiation Damage Processes in Iron", Proceedings of the The Fourth Pacific Rim International Conference on Advanced Materials and Processing (PRICM4), Ed. By S. Hanada, Z. Zhong, S.W. Nam and R.N. Wright, The Japan Institute of Metals (2001) 1383.

C15. B.D. Wirth, G.R. Odette and R.E. Stoller, "Recent Progress Toward an Integrated Multiscale-Multiphysics Model of Reactor Pressure Vessel Embrittlement", MRS Soc. Symp. Proc 677 (2001) AA5.2.

C14. B.D. Wirth, P. Asoka-Kumar, R.H. Howell, G.R. Odette, and P.A. Sterne, "Positron Annihilation Spectroscopy and Small Angle Neutron Scattering Characterization of Nanostructural Features in Irradiated Fe-Cu-Mn Alloys", MRS Soc. Symp. Proc 650 (2001) R6.5.

C13. B.D. Wirth, V.V. Bulatov and T. Diaz de la Rubia, "Atomistic Simulation of Dislocation-Defect Interactions in Cu", MRS Soc. Symp. Proc 650 (2001) R3.27.

C12. J. Marian, B.D. Wirth, J.M. Perlado, T. Diaz de la Rubia, R. Schaublin, D. Lodi, M. Hernandez, G. de Diego and R. E. Stoller, "Direct Comparison between Modeling and Experiment: An a-Fe Ion Implantation Study", MRS Soc. Symp. Proc 650 (2001) R3.2.

C11. J. Marian, B.D. Wirth, J.M. Perlado, G.R. Odette and T. Diaz de la Rubia, "Atomistic Simulation of Vacancy and Self-Interstitial Diffusion in Fe-Cu Alloys", MRS Soc. Symp. Proc 650 (2001) R6.9.

C10. B.D. Wirth and G.R. Odette, "Kinetic Lattice Monte Carlo Simulations of Cascade Aging in Iron and Dilute Iron-Copper Alloys", MRS Soc. Symp. Proc. 540 (1999), 637.

C9. B.D. Wirth and G.R. Odette, "A Comparison of Embedded Atom Versus Nearest Neighbor Pair Potential Kinetic Lattice Monte Carlo Simulations of Diffusion and Decomposition Kinetics in Iron-Copper Alloys", MRS Soc. Symp. Proc. 481 (1998) 151.

C8. B.D. Wirth, G.R. Odette, D. Maroudas, and G.E. Lucas, "Simulation of Interstitial Cluster Mobility and Cluster Mediated Surface Topologies", MRS Soc. Symp. Proc. 504 (1998) 63.

C7. B.D. Wirth, G.R. Odette, W.A. Pavinich, G.E. Lucas, and S. Spooner, "Small Angle Neutron Scattering Study of Linde80 RVSP Welds", Effects of Radiation on Materials: 18th Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials (1999) 102.

C6. M.A. Sokolov, S. Spooner, G.R. Odette, B.D. Wirth, and G.E. Lucas, "SANS Study of High-Copper RPV Welds", Effects of Radiation on Materials: 18th Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials (1999) 333.

C5. G.R. Odette, G.E. Lucas, B. Wirth, and C.-L. Liu, "Current Understanding of the Effects of Environmental and Irradiation Variables on RPV Embrittlement", Proceedings of the US NRC Twenty Fourth Water Reactor Safety Information Meeting, (NUREG/CP-0157). Washington, DC: Nucl. Regul. Comm., vol. 2 (1997) 1-23.

C4. G.R. Odette, C.-L. Liu, and B.D. Wirth, "On the Composition and Structure of Nanoprecipitates in Irradiated Pressure Vessel Steels", MRS Soc. Symp. Proc. 439 (1997) 457.

C3. G.E. Lucas, G.R. Odette, K. Edsinger, B. Wirth, and J.W. Sheckherd, "On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels", Effects of Radiation on Materials 17th Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials (1996) 790.

C2. B. Wirth, K. Edsinger, G.R. Odette, and G.E. Lucas, "Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction", Effects of Radiation on Materials 17th Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials (1996) 706.

C1. K. Edsinger, G.R. Odette, G.E. Lucas, and B. Wirth, "The Effect of Constraint on Toughness of a Pressure Vessel Steel", Effects of Radiation on Materials 17th Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials (1996) 670.


NON-REFEREED PUBLICATIONS (in archival magazines, journals or book chapters):

F4. G.R. Odette and B.D. Wirth, "Radiation Effects in Fission and Fusion Reactors", contributed article in Handbook of Materials Modeling, Volume I: Methods and Models (Springer, Netherlands, 2005) Article 2.29.

F3. B.D. Wirth, A.J. Schwartz, M.J. Fluss, M.J. Caturla, M.A. Wall and W.G. Wolfer, "Fundamental Studies of Plutonium Aging", MRS Bulletin, 26 (2001) 679.

F2. G. R. Odette, B. D. Wirth, D. J. Bacon and N. M. Ghoneim, "Multiscale-Multiphysics Modeling of Radiation-Damaged Materials: Embrittlement of Pressure Vessel Steels", MRS Bulletin, 26 (2001) 176.

F1. B.D. Wirth, M.J. Caturla and T. Diaz de la Rubia, "Modeling and Computer Simulation: Molecular Dynamics and Kinetic Monte Carlo", Encyclopedia of Materials, (2001)


Chairing of Technical Meetings and Workshop Programs


Refereeing/Reviewing Activity

- DOE Office of Nuclear Energy, Science and Technology (NE) Nuclear Energy Research Initiative (NERI) program

- DOE Office of Basic Energy Science (OBES) University Nanoscience Initiative program

- U.S. Civilian Research and Development Foundation (CRDF), Science and Technology Center of Ukraine (STCU) program

- Journal of Nuclear Materials, Computational Materials Science, American Society of Testing and Materials, Philosophical Magazine A, Physical Review B, Physic Scripta, Nuclear Instruments & Methods B


Professional Societies


TECHNICAL PRESENTATIONS

Invited Technical Presentations:

26. B.D. Wirth, A. Arsenlis, J. Marian, G.R. Odette, J.S. Robach, I.M. Robertson, R. Schaublin, L. Ventelon, J.A. Young and L.A. Zepeda-Ruiz, "Multiscale modeling of radiation damage accumulation in bcc and fcc metals in the fusion environment", 11th International Conference on Fusion Reactor Materials, Kyoto, Japan, December 2003.

25. B.D. Wirth, J. Marian, J.A. Young, E.M. Bringa, J. Robach and I.M. Robertson, "Atomistic simulations of dislocation interactions, Plasticity 2003, Quebec City, Canada, 12 July 2003.

24. B.D. Wirth, "Multiscale Modeling of Radiation Damage Mechanisms", DOE Office of Science briefing for Dr. Raymond Orbach, Washington, DC, 19 May 2003.

23. B.D. Wirth, P. Asoka-Kumar, R.H. Howell, J. Marian, M.K. Miller, G.R. Odette, and P.A. Sterne, "Characterization of nanostructural features in irradiated reactor pressure vessel steels: implications for nuclear reactor lifetime extension", University of Michigan, Nuclear Engineering Department Colloquium, Ann Arbor, MI, 15 November 2002.

22. B.D. Wirth, G.R. Odette, P. Asoka-Kumar, P.A. Sterne, R.H. Howell, M.K. Miller, and R.E. Stoller, "Experimental Evidence for Defect Accumulation: Positron Annihilation and Neutron Scattering", IEA Materials Modeling Workshop, Les Diablerets, Switzerland, 1-4 October 2002.

21. B.D. Wirth, A. Arsenlis, P. Asoka-Kumar, E.M. Bringa, M.J. Caturla, T. Diaz de la Rubia, J. Marian, G.R. Odette, I. Robertson, J. Robach, R. Schaublin, P.A. Sterne, and R.E. Stoller, "Multiscale Modeling of Radiation Damage Mechanisms", University of California, Berkeley, Nuclear Engineering Department Colloquium, Berkeley, CA, 23 September 2002.

20. B.D. Wirth, E.M. Bringa, M.J. Caturla, A. Kubota, J. Stolken, T. Diaz de la Rubia and J. Wark, "Atomistic Simulations of High-Strain Rate Deformation in Metals", Russian-U.S. Workshop on Plutonium Science, VNIIEF, Sarov, Russia, 24-27 June 2002.

19. B.D. Wirth, J. Marian, E.M. Bringa, and G.R. Odette, "Modeling Cascade Aging and the Formation of Vacancy-Solute Clusters in Fe-based Alloys", to be presented at the Symposium on the Mechanics of Materials at the Nano- and Micro-scale, First International Conference on Multiscale Materials Modeling, London, 17-20 June 2002.

18. B.D. Wirth and G.R. Odette, "Recent Progress towards a Mechanistic Model of Reactor Pressure Vessel Embrittlement", International Symposium on the Mechanisms of Material Degradation and Non-Destructive Evaluation in Light Water Reactors, Osaka, Japan, 27 May 2002.

17. B.D. Wirth and T. Diaz de la Rubia, "State-of-the-art in Multiscale Materials Modeling: Atoms to Performance", Multiscale Modeling of Materials: Performance and Discovery Workshop, ExxonMobil, Clinton, NJ, 9 May 2002.

16. B.D. Wirth, E.M. Bringa, M.J. Caturla, T. Diaz de la Rubia, J. Young, J. Marian, G.R. Odette, R. Schaublin, and R.E. Stoller, "Mechanistic Insights from Multiscale Modeling of Environmentally Induced Materials Degradation", Multiscale Modeling of Materials: Performance and Discovery Workshop, ExxonMobil, Clinton, NJ, 9 May 2002.

15. B.D. Wirth, E.M. Bringa, M.J. Caturla, T. Diaz de la Rubia, J. Young, J. Marian, G.R. Odette, R. Schaublin, and R.E. Stoller, "Multiscale Modeling of Radiation Damage Mechanisms", University of New Mexico, Mechanical Engineering Department Colloquium, Albuquerque, NM, 23 April 2002.

14. B.D. Wirth, P. Asoka-Kumar, R.H. Howell, J. Marian, M.K. Miller, G.R. Odette, and P.A. Sterne, "Characterization of nanostructural features in irradiated reactor pressure vessel steels: implications for nuclear reactor lifetime extension", University of Wisconsin, Engineering Physics Department Colloquium, Madison, WI, 2 April 2002.

13. B.D. Wirth, P. Asoka-Kumar, R.H. Howell, J. Marian, M.K. Miller, G.R. Odette, and P.A. Sterne, "Characterization of nanostructural features in irradiated reactor pressure vessel steels: implications for nuclear reactor lifetime extension", University of California, Berkeley, Nuclear Engineering Department Colloquium, Berkeley, CA, 13 March 2002.

12. B.D. Wirth, N.M. Ghoniem, H.L. Heinisch, R.J. Kurtz, G.R. Odette, D. Srolovitz, R.E. Stoller, H.M. Zbib and S.J. Zinkle, "Multiscale Modeling of Radiation Damage in Fusion Reactor Materials", DOE Office of Fusion Energy Sciences Science in Technology Seminar, Gaithersburg, MD, 12 March 2002.

11. B.D. Wirth, G.R. Odette, R.D. Klingensmith, G.E. Lucas, P. Asoka-Kumar, R.H. Howell, and P.A. Sterne, "SANS Application to metallurgy: Characterization of Nanostructural Features in Irradiated Reactor Pressure Vessel Steels and Implications for Nuclear Reactor Lifetime Extension", University of Indiana LENS Workshop, 16 November 2001.

10. B.D. Wirth, G.R. Odette, R. E. Stoller, J. Marian, M.J. Caturla, V.V. Bulatov, T. Diaz de la Rubia, H. Zbib, P.A. Sterne, P. Asoka-Kumar and R.H. Howell, "Recent Progress Toward Multiscale Modeling of Radiation Damage in Structural Materials", American Institute of Chemical Engineers Fall 2001 Meeting, Reno, NV, 9 November 2001.

9. B.D. Wirth, "Computational Materials Science as it Relates to Energy/Power", National Academy of Sciences, Panel on Materials Research for Defense After-Next, Irvine, CA, 11 October 2001.

8. B.D. Wirth, J. Young, V.V. Bulatov and T. Diaz de la Rubia, "Atomistic Insight into Dislocation - Defect Interactions", Multiscale Modeling of Materials Strength and Deformation Workshop, Bodega Bay, CA, 7 October 2001.

7. B.D. Wirth, R.H. Howell, P. Asoka-Kumar, P.A. Sterne, M.J. Caturla, J. Marian, T. Diaz de la Rubia, V.V. Bulatov, G.R. Odette, H.M. Zbib, T. Khraishi, R.E. Stoller, R. Schaueblin and M. Victoria, "An Integrated Experimental and Multiscale Modeling Program to Characterize Irradiated Microstructures in Light Water Reactor Steels", Bettis Atomic Power Laboratory, Pittsburgh, PA, May 2001.

6. B.D. Wirth, T. Diaz de la Rubia and Y. Osetsky, "Atomistic Simulations of Dislocation-Defect Interactions", First International Energy Agency Fusion Materials Modeling Workshop, San Francisco, CA, April 2001.

5. B.D. Wirth, M.J. Caturla, N. Soneda, E. Alonso, R. Schaublin and T. Diaz de la Rubia, "Modeling Radiation Damage in FCC and BCC Materials", Computer Simulation of Radiation Effects (COSIRES 2000), State College, PA, July 2000.

4. B.D. Wirth, V. Bulatov and T. Diaz de la Rubia, "Dislocation - SFT Interactions in Cu", International Workshop on Dislocation - Defect Interactions in Irradiated Materials, Toledo, Spain, April 2000.

3. B.D. Wirth, G.R. Odette, G.E. Lucas, R.D. Klingensmith and M.A. Sokolov, "SANS Studies of CRP Evolution in RPV Steels", Research Assistance Task Force Meeting on Radiation Materials Science Applied to Reactor Pressure Vessel Embrittlement Meeting, Charleston, SC, September 1999.

2. B.D. Wirth, "On the Character of Nanoscale Reatures in Irradiated Reactor Pressure Vessel Steels", Lawrence Livermore National Laboratory, Livermore, CA, June 1998.

1. B. D. Wirth, "The Character of Nano-Scale Features in Reactor Pressure Vessel Steels Under Neutron Irradiation", NASA NAS Nanotechnology Seminar, Mountain View, CA, January 1998.