ML071800287
| ML071800287 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/25/2007 |
| From: | Uttal S NRC/OGC |
| To: | |
| S L Uttal, NRC/OGC, 301-415-1582 | |
| Shared Package | |
| ML071800194 | List: |
| References | |
| 50-293-LR, ASLBP 06-848-02-LR, RAS 13821 | |
| Download: ML071800287 (6) | |
Text
NATHAN E. BIXLER Phone: 505-845-3144 Mail Stop: 0748 Fax: 505-844-2829 Email: nbixler@sandia.gov EDUCATION:
1982 Ph.D., Chemical Engr, U OF MINNESOTA - MINNEAPOLIS, MN 1976 Bachelors, Chemical Engr, UNIVERSITY OF TOLEDO, OH 1972 HS, College Prep, SWANTON HIGH SCHOOL, OH WORK EXPERIENCE:
1982-Present: Sandia National Laboratories 1997-present: Principal Member of the Technical Staff working in nuclear accident progression and consequence analysis for NRC (VICTORIA, RADTRAD, MACCS2, WinMACCS, MEL-MACCS, and SECPOP2000 codes); Performing safety analysis for Mars Science Laboratory Mission for DOE and NASA 1989-1995: Senior Member of the Technical Staff working in nuclear accident progression analy-sis for NRC (VICTORIA code) 1982-1989: Member of the Technical Staff working in fluid mechanics and heat transfer support-ing the Yucca Mountain and WIPP projects SPECIAL SKILLS:
Fluid Mechanics, Free Surface Flows, Heat Transfer, Porous Flows, Computer Code Development, Computer Simulation, In-Vessel Analysis of Fission Product Behavior (Level-2 PRA), Nuclear Accident Consequence Analysis (Level-3 PRA)
PUBLICATIONS:
Bixler, N. E. and Martinez, M. J.
Radionuclide Transport Code Development in Support of Nuclear Waste Storage Investigations SAND83-0660, 1983 Bixler, N. E., Mondy, L. A., and Wilson, R. K.
Comparison of Waste Emplacement Configurations for a Nuclear Waste Repository in Tuff, IV.
Thermo-Hydrological Analysis SAND83-0757, 1983 Bixler, N. E. and Eaton, R. R.
Sensitivity of Calculated Hydrological Flows Through Multilayered Hard Rock to Computational Solution Procedures Proc. Symposium on Groundwater Flow and Transport Modeling for Performance Assessment of Deep Geologic Disposal of Radioactive Waste: A Critical Evaluation of the State of the Art, 1985
Bixler, N. E. and Benner, R. E.
Finite Element Analysis of Axisymmetric Oscillations of Sessile Liquid Drops Numerical Methods in Laminar and Turbulent Flow, Part II, 1985 Eaton, R. R., Bixler, N. E., and Reda, D.
Coupled Hydrothermal Flows of Liquid and Vapor in Welded Tuff: Numerical Modeling of Pro-posed Experiment Coupled Processes Associated with Nuclear Waste Repositories, 1985 Bixler, N. E.
NORIA--A Finite Element Computer Program for Analyzing Water, Vapor, and Energy Transport in Porous Media SAND84-2057, 1985 Eaton, R. R. and Bixler, N. E.
Analysis of a Multiphase, Porous-Flow Imbibition Experiment in Fractured Volcanic Tuff Proc. Symposium on Flow and Transport through Unsaturated Fractured Rock, Geophysical Monograph 42, 1986 Bixler, N. E. and Carrigan, C. R.
Enhanced Heat Transfer in Partially Saturated Hydrothermal Systems Geophysical Research Letters, Vol. 13, 1986 Bixler, N. E. and Scriven, L. E.
Downstream Development of Three-Dimensional Viscocapillary Film Flow Industrial Engineering Chemistry Research, vol. 26, 1987 Bixler, N. E., Eaton, R. R., and Russo, A. J.
Drying Analysis of a Multiphase, Porous-Flow Experiment in Fractured Volcanic Tuff Fundamentals of Heat Transfer in Drying, 1987 Bixler, N. E. and Kraynik, A. M.
The Onset of Taylor Vortices in Flows with a Circumferential Pressure Gradient: Application to the Helical Screw Rheometer Canadian Congress on Applied Mechanics, 1987 Bixler, N. E. and Carrigan, C. R.
Finite Element Analysis of Heat Transfer in a Hydrothermal Zone Numerical Methods in Thermal Problems, vol. 5, 1987 N. E. Bixler An Improved Time Integrator for Finite Element Analysis Communications in Applied Numerical Methods, 1989 Eaton, R. R., Bixler, N. E., and Gartling, D. K.
Effect of Pressure Basis Functions on Predicted Water Velocities for Flow in Fractured Rock
Journal of Contaminant Transport, 1989 Bixler, N. E. and Carrigan, C. R.
Finite Element Analysis of a Darcy Velocimeter in a Variably Saturated Soil Proceedings of the 7th International Symposium on Finite Element Methods in Flow Problems, 1989 T. J. Heames, Williams, D. A., Bixler, N. E., et al.
VICTORIA: A Mechanistic Model of Radionuclide Behavior in the Reactor Coolant System Under Severe Accident Conditions NUREG/CR-5545, SAND90-0756, 1990 Bixler, N. E. and Heames, T. J.
Status of VICTORIA Development and Assessment Proceedings of the 18th Water Reactor Safety Information Meeting, 1990 Bixler, N. E. and Heames, T. J.
VICTORIA: A Code for Analyzing Severe Nuclear Accidents Proceedings of the 6th Miami International Symposium on Heat & Mass Transfer, 1990 Bixler, N. E., Heames, T. J., and Powers, D. A.
VICTORIA-92 and Its Application to the Phebus-FPT0 Test, Proceedings of the Twentieth Water Reactor Safety Information Meeting, 1992 T. J. Heames, Williams, D. A., Bixler, N. E., et al.
VICTORIA: A Mechanistic Model of Radionuclide Behavior in the Reactor Coolant System Under Severe Accident Conditions NUREG/CR-5545, SAND90-0756 Rev. 1, 1992 Bixler, N. E.
Model for Heat-Up of Structures in VICTORIA SAND92-1506, 1993 Bixler, N. E. and Erickson, C. E.
VICTORIA-92 Pretest Analysis of PHEBUS-FPT0 SAND93-2275, 1994 Bixler, N. E. and Erickson, C. E.
Investigation of a Steam Generator Tube Rupture Sequence Using VICTORIA Proceedings of the Twenty-Third Water Reactor Safety Information Meeting,1996 Bixler, N. E. and Schaperow, J. H.
The Effect of the Number of Condensed Phases Modeled on Aerosol Behavior During an Induced Steam Generator Tube Rupture Sequence Proceedings of the Third OECD Specialists Meeting on Nuclear Aerosols in Reactor Safety, 1998
Bixler, N. E., Cole, R. K., Young, M. F., Gauntt, R. O., and Schaperow, J. H.
Recent MELCOR and VICTORIA Fission Product Research at the NRC Proceedings of the Twenty-Fifth Water Reactor Safety Information Meeting, 1998 Bixler, N. E.
VICTORIA 2.0: A Mechanistic Model for Radionuclide Behavior in a Nuclear Reactor Coolant System Under Sever Accident Conditions NUREG/CR-6131, SAND93-2301, 1998 Bixler, N. E. and Erickson, C. M.
RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation NUREG/CR-6604, Supp. 1, SAND98-0272/1, 1999 N. E. Bixler and R. D. Gasser Recent Plant Studies Using VICTORIA 2.0 Proceeding of ICONE8, 2000 N. E. Bixler, D. I. Chanin, K. L. McFadden, and D. W. Whitehead Current Activities to Enhance the MACCS2 Code at Sandia National Labs Proceedings of the ANS Annual Meeting, 2001 N. E. Bixler, A. B. Baker, W. E. Beyeler, S. H. Conrad, D. L. Harris, L. A. Malczynski, and P. E.
Rexroth Global Energy Futures Model Proceedings of ICONE10, 2002 N. E. Bixler, K. L. McFadden, and J. E. Cash Future Plans for MACCS2 Proceedings of the Fourth International MACCS Users Group Meeting, 2002 N. E. Bixler, D. W. Whitehead, J. J. Gregory, C. A. Ottinger, T. D. Brown, and J. A. Mitchell Methodology for a Level 3 PRA Analysis of a Nuclear Reactor Accident Using MACCS2 Proceedings of PSAM6, 2002 N. E. Bixler, R. D. Waters, and D. W. Whitehead Uncertainty Analysis with MACCS2 Using Data Based on Expert Elicitation American Metrological Society Annual Meeting, 2002 N. E. Bixler, S. A. Shannon, C. W. Morrow, B. E. Meloche, and J. N. Ridgely SECPOP2000: Sector Population, Land Fraction, and Economic Estimation Program NUREG/CR-6525 Rev. 1, SAND2003-1684P, 2003 J. A. Mitchell, C. Molenkamp, N. E. Bixler, C. Morrow, and J. V. Ramsdell Comparison of Average Transport and Dispersion Among a Gaussian Model, a Two-Dimensional Model and a Three-Dimensional Model Proceedings of PSAM7, 2004
N. E. Bixler, C. W. Morrow, J. M. Phillips, M. Fatenejad, and J. Mitchell Assessment of Uncertain Input Data, Methodology, and Results for a Level 3 PRA Analysis of a Nuclear Reactor Accident Using MACCS2 Proceedings of PSAM7, 2004 N. E. Bixler, J. W. Braithwaite, and D. G. Robinson A Perspective on Risk/Reliability Estimation in the Presence of Aging Incorporating PSA Into Ageing Management, 2004 N. E. Bixler and R. O. Gauntt A Methodology for Performing Consequence Analyses in Support of Level -3 PRAs Proceedings of ANS Probabilistic Safety Analysis Meeting, 2005 S. Ashbaugh, N. E. Bixler, and M. Leonard Accident Progression and Source Term Analysis for Short-Term Station Blackout Scenarios in a BWR with a Mark III Containment SAND2005-6116, 2005 N. E. Bixler, K. L. McFadden, and C. W. Morrow Current Status of the MACCS2 and WinMACCS Codes EFCOG/SAWG Workshop, 2005 N. E. Bixler, V. D. Cleary, and J. Joonyub MACCS2 Consequence Calculations for a Postulated Short-Term Station Blackout at a Pressur-ized Water Reactor with an Ice Condenser Containment and a Boiling Water Reactor with a Mark III Containment SAND2006-0632, 2005 N. E. Bixler et al.,
Sandia Support of the NRC's Nuclear Power Plant Vulnerability to Aircraft Attack Program SAND2006-1284P T. J. Bartel, G. C. Bessette, N. E. Bixler, B. P. Danowsky, C. A. Glissman, R. J. Lipinski, D. L.
Potter, D. A. Powers, and D. G. Robinson Preliminary Safety Analysis Report for the Mars Science Laboratory MMRTG Launch Approval SAND2006-7312 SUPPLEMENTARY ACHIEVEMENTS:
Received SAFE Award for defending VICTORIA during the VICTORIA Independent Peer Review (V. Mubayi et al., BNL Tech Rep. W-6436, 1997)
Employee Recognition Award for Nuclear Power Plant Vulnerability Analysis Team, 2004 Employee Recognition Award for Research and Test Reactor Vulnerability Assessment Team, 2005 Best Presentation Award for EFCOG/SAWG Workshop, 2005 Employee Recognition Award for Radioisotope System Launch Safety Team, 2007 Lead trainer for NRCs Accident Consequence Analysis P-301 Course, 2003-present
REFERENCES:
John E. Kelly, Department 6870, Sandia National Labs, 844-8993 Dana A. Powers, Department 6870, Sandia National Labs, 845-9838 Randall O. Gauntt, Department 6762, Sandia National Labs, 844-2829 Jocelyn A. Mitchell, Office of Research, Nuclear Regulatory Commission, 301-415-5289 Jason H. Schaperow, Office of Research, Nuclear Regulatory Commission, 301-415-5907