William E. Burchill

Adjunct Professor & Retired Department Head, Nuclear Engineering

Date of Appointment: 2003

Office: 129 Zachry Engineering Center
Phone: 979/845-1670
Fax: 979/845-6443
E-mail: burchill@ne.tamu.edu

Mailing Address: Texas A&M University
Department of Nuclear Engineering
3133 TAMU
College Station, TX 77843-3133

Education
M.S. Management, Hartford Graduate Center of Rensselaer Polytechnic Institute, 1986
Ph.D. Nuclear Engineering, University of Illinois, 1970
M.S. Nuclear Engineering, University of Illinois, 1965
B.S. Metallurgical Engineering, Missouri School of Mines & Metallurgy, 1964

Current Courses

NUEN 101, Introduction to Nuclear Engineering
NUEN 609, Nuclear Safety
NUEN 489, Nuclear Safety
NUEN 489, PRA

Areas of Interest

Nuclear power: interests include power uprates, license renewal, BWR internals integrity, PWR steam generator degradation, PWR reactor vessel degradation, power distribution stability, extended fuel burnup, instrumentation and controls upgrades, equipment reliability and availability improvement, and public information improvement.

Nuclear safety: interests include reactivity anomalies, large break LOCA frequency, small break LOCA thermal-hydraulic phenomena, ATWS frequency, control rod ejection consequences, common mode failure precursors, high temperature induced SGTR, and accident precursor analysis.

Risk management (PRA): interests include on-line risk management, outage risk management, transition risk modeling, external events risk modeling, risk-informed technical specifications, risk-informed in-service inspection, risk-informed in-service testing, human reliability analysis, common mode failure rates, large fault tree modeling, large event tree modeling, and severe accident phenomena.

Reactor regulation: interests include risk-informed reactor oversight; risk-informed safety classification of systems, structures, and components; risk-informing current regulations; risk-informed regulatory structure; risk-based regulatory structure; risk acceptance criteria; risk-informed/based regulation versus deterministic regulation; and regulation of advanced reactor designs.

Reactor operations: interests include on-line maintenance, outage optimization, reactor operator training, full-scope simulator modeling, fuel cycle optimization, reliability-centered maintenance, emergency response scenario development, emergency procedures improvement, and improved fuel utilization.

Reactor design: interests include design basis definition, risk-informed design basis modification, design process optimization, design methods, design controls, quality assurance, quality control, statistical analysis of operations, evolutionary reactor designs, advanced reactor designs, and innovative reactor designs.

Curriculum Vita

SUMMARY

Engineering executive leading the largest United States university nuclear engineering department. Skilled in preparing proposals, obtaining funding, and managing R&D programs. Effective at organizing resources, prioritizing tasks and making decisions. Excellent interpersonal communication and public speaking skills. Leader on prominent nuclear power regulatory issues. Record of achieving innovative solutions to complex problems.

ACADEMIC LEADERSHIP EXPERIENCE

Contributions to Scholarship

Heads Texas A&M University Nuclear Engineering Department. Developed and taught graduate level engineering courses and industrial short courses and seminars. Directed nuclear training center which provided classroom and simulator training to over 3,500 nuclear power reactor operators.

• Developed and taught Ph.D. "Nuclear Safety" course and M.S. "Reactor Design" and "Safety Systems and Controls" courses.
• Presented invited seminars at Massachusetts Institute of Technology, University of Illinois, University of Missouri, Columbia University, and University of Taiwan.
• Presented lectures on nuclear safety at Massachusetts Institute of Technology, Northwestern University, and International Center for Heat and Mass Transfer (Yugoslavia).
• Improved Combustion Engineering (C-E) nuclear training center by upgrading all nuclear steam supply system (NSSS) models on nuclear power plant control room training simulator.
• Helped plan curriculum of first ABET accredited Nuclear Engineering Technology Program.

Research and Development

Heads Texas Engineering Experiment Station Nuclear Engineering Division. Directed business units which developed new products and services to meet regulatory requirements and to improve plant safety and capacity factor. Managed preparation of proposals, obtained both private and public funding, and conducted numerous R&D programs.

• Managed program to develop, to test, and to gain government approval of new safety systems installed in 30 nuclear power plants since the Three Mile Island accident.
• Managed development of NSSS vendor proprietary digital computer codes used to analyze all reactor transients and accidents in license applications.
• Developed first-principles, real-time nuclear power plant simulation software which is installed on nuclear training simulators and workstation-based plant analyzers worldwide.
• Managed experimental R&D program to investigate reactor fuel failure during accidents.
• Evaluated data from experimental nuclear reactor safety programs conducted at the Idaho National Engineering Laboratory and used results to develop safety analysis methods.
• Developed understanding of steam-water mixing phenomena as Principal Investigator of U.S. Atomic Energy Commission [now Nuclear Regulatory Commission (NRC)] contract.
• Conducted research projects at Monsanto Research Corporation Mound Laboratory and Argonne National Laboratory to determine nuclear reactor materials engineering properties.
• Developed confirmation of various analytical theories by experimental Ph. D. Thesis: "Statistical Properties of Velocity and Temperature in Isothermal and Non-isothermal Turbulent Pipe Flow."
  

Advancement of Engineering

Organized numerous technical programs as a member of American Nuclear Society (ANS) Nuclear Reactor/Installations Safety and Education and Training Divisions. Presented and published technical papers and made recommendations as reviewer of many technical publications.

• Wrote over thirty-five technical papers in journals, proceedings, and transactions (see addendum).
• Contributed chapters on loss of coolant accident (LOCA) and anticipated transients without scram (ATWS) to textbook, Guidebook to Light Water Reactor Safety Analysis, Hemisphere Publishing Corp. (1985).
• Organized programs for ANS Nuclear Safety Topical Meetings in 1977, 1983, 1986 and 1988, 1991, 2002.
• Organized programs for the Symposium on the Training of Nuclear Facility Personnel (the "Gatlinburg Symposium"), 1985, 1987, 1989, and 1991.
• Recommended revisions to many technical publications as reviewer for the ANS journals Nuclear Technology and Nuclear Science and Engineering since 1983.
• Helped organize program for the first ANS "Workshop on Safety of Soviet-Designed Nuclear Power Plants" and provided session report, 1992.

ADMINISTRATIVE LEADERSHIP EXPERIENCE

Business Management

Directed profit center business units with annual revenue over $20MM during each of the most recent five years. Initiated and directed numerous changes in business composition in response to market conditions. Managed both home and field engineering offices.

• Produced profits above plan in five of last six years by aggressive marketing and controlling costs.
• Increased revenue by 500% in first six years by providing high quality services and diversifying into new markets.
• Started training simulator upgrade business and built it into $5MM/year international success in less than three years.
• Unified analysis services business providing safety analysis, reliability analysis and PRA's; result was profit of 300% of plan in first year.
• Developed new venture government services business at Savannah River Site and expanded to $19MM annual revenue in three years.

Management Improvement

Recruited by corporate management of two utilities to reorganize and to improve major Nuclear Department functions. Restructured risk management functions in corporate and regional engineering offices and ten nuclear plants and hold leadership positions in industry/NRC risk-informed regulation initiative. Restructured seven assessment functions to produce more timely and higher quality information for senior management.

• Initiated significant risk-informed licensing improvements which contributed to major performance turnaround in largest U.S. nuclear utility.
• Led merger of Commonwealth Edison, Philadelphia Electric, and Amergen risk management activities.
• Played an important role in Susquehanna Steam Electric Station achieving all NRC Systematic Assessment of Licensee Performance (SALP) 1 ratings in 1995.
• Designed a new employee compensation system as a member of a Corporate Compensation Team.
• Implemented a new, consolidated deficiency identification and corrective action system.
  

Nuclear Safety

Upgraded risk management decision processes for largest U.S. nuclear utility. Directed independent assessments of nuclear power plant safety. Managed preparation of safety analysis reports, topical reports, design backfit packages, and comments on generic safety issues. Presented results to enforcement conferences and meetings of NRC and Advisory Committee on Reactor Safeguards (ACRS).

• Upgraded PRA tools and standardized risk management practices at ten nuclear power plants.
• Conceived and introduced significant safety assessment technique improvements through variation of assessment patterns, use of intrusive methodology, and application of inferential approaches.
• Developed and applied PRA-based design decision tools for the System 80+ ALWR (advanced light water reactor) to support design certification by the NRC.
• Designed and implemented programs for design basis reconstitution, configuration management, technical specification standardization, emergency operating procedure upgrades, shutdown risk reduction, station blackout, and severe accident management.
• Formulated function-based emergency procedure guidelines and convinced NRC of the necessity to have functional recovery paths.
• Developed and managed licensing of small break LOCA analysis methods in response to Atomic Energy Commission's Final ECCS (emergency core cooling system) Acceptance Criteria.

International Contracts

Developed and managed contracts in several European countries. Arranged and administered expatriate assignments of technical personnel to and from numerous European and Pacific Basin countries.

• Started and directed international training simulator upgrade business including supply of all NSSS simulation software for Sizewell B nuclear training simulator.
• Presented technical seminars in South Korea and Taiwan to support NSSS sales.
• Conducted technology transfer discussions in Germany, Russia, Finland, Canada, Spain, United Kingdom, Mexico and Belgium.
• Developed and administered training programs for technical personnel in twelve job classifications from South Korea nuclear power plants.
• Trained personnel from several European countries in nuclear power plant simulation and PSA techniques.
  

ACADEMIC POSITIONS

Professor and Department Head, Nuclear Engineering, Texas A&M University, and Division Head, Nuclear Engineering, Texas Engineering Experiment Station, 2003 - present.

Invited Lecturer on Nuclear Power Reactor Transients and Accidents, Institute of Nuclear Power Operations course, Nuclear Technology for Utility Executives, Massachusetts Institute of Technology, 1993-2002.

Invited Lecturer in International Atomic Energy Agency Inter-regional Training Courses, Nuclear Power Operational Safety, Argonne National Laboratory, 2000-2002.

Constituent Alumni Industry Advisory Board, Nuclear, Radiological and Plasma Engineering Department, University of Illinois, 2000-2002.

Nuclear Engineering Technology Advisory Committee, Thames Valley State Technical College (now renamed Three Rivers Community College), Norwich, Connecticut, 1988-1994.

Adjunct Lecturer on Nuclear Reactor Safety Control, The Hartford Graduate Center of Rensselaer Polytechnic Institute, Hartford, Connecticut, 1984-1985.

Invited Lecturer on Nuclear Reactor Accidents, Continuing Education Course: Safety of Light-Water-Cooled Nuclear Power Plants, The Technological Institute of Northwestern University, Evanston, Illinois, 1982-1987.

Visiting Associate Professor of Nuclear Engineering, Texas A&M University, College Station, Texas, 1982-1983.

Invited Lecturer on Nuclear Reactor Safety, Advanced Course: Nuclear Reactor Safety Assessments, International Center for Heat and Mass Transfer, Dubrovnik, Yugoslavia, 1981.

INDUSTRY POSITIONS

EXELON NUCLEAR

Director, Risk Management 1998-2003

PENNSYLVANIA POWER & LIGHT CO.

Manager, Nuclear Assessment Services 1995-97 Member, Susquehanna Review Committee 1995-97

COMBUSTION ENGINEERING

Project Director, Engineering Operations 1994 Manager, ATWS Task Force 1978-79
Director, Operations Svcs. & Field Engrg. 1991-93 Section Manager, ECCS Development 1977-78
Director, Nuc. Trng. & Operations Svcs. 1985-91 Supervisor, NSSS Simulations 1974-77
Director, Nuclear Training 1983-85 Supervisor, Small Break LOCA Analysis 1973-74
Visiting Associate Professor (see above) 1982-83 Principal NSSS Engr., Experimental Modeling 1972-73
Manager, C-E Owners Group Programs 1979-82 Senior NSSS Engr., LMFBR Core Design 1970-72

MANAGEMENT TRAINING

Management Development Program, Center for Creative Leadership, 1996
Manager of Managers Program, ABB, 1993
Root Cause Evaluation Seminar, ABB, 1992
Finance & Accounting Program, ABB, 1991
Quality Education System Training, Phillip Crosby Associates, 1989
Effective Client Relations, Professional Management Institute, 1989
Working Capital Management Program, C-E, 1986
Management Development Program, Hartford Graduate Center, 1984
Middle Management Workshop, Practical Management Associates, 1984
Management Leadership Workshop, Nordli, Wilson Associates, 1978
Supervisory Management Course, American Management Associates, 1976
Supervisory Management Workshop, Practical Management Associates, 1973

AWARDS/COMMENDATIONS

Atomic Energy Commission Nuclear Science and Engineering Fellowships, 1964-1967.
University of Illinois Graduate Fellowships, 1968-1970.
C-E Outstanding Service Award for contributions to C-E response to the Three Mile Island accident, 1979.
Combustion Engineering Management Performance Incentive Program Awards, 1984-1993.
ANS Presidential Citation for contributions to the advancement of nuclear science and technology, 1994.
Pennsylvania Power & Light Co. Management Incentive Compensation Awards, 1995-1996.
Exelon Nuclear (Commonwealth Edison) Incentive Compensation Awards, 1998-2002.

PROFESSIONAL ACTIVITIES

Nuclear Energy Institute

Risk Informed Regulation Part 50 Task Force 1999-2003
Circuit Failures Task Force 1999-2002

INPO

Supplier-Participant Advisory Committee, Institute of Nuclear Power Operations 1992-1994

American Nuclear Society (partial listing)

• President 2008-2009
• Vice-President/President Elect 2007-2008
• Risk-Informed Standards Committee Chair 2006-2008
• Standards Board 2006-2008
• Risk-Informed Standards Committee 2005-2008
• Nuclear Risk Management Coordinating Committee 2004-2007
• PSA '05 (Probabilistic Safety Analysis Topical Meeting) Program Committee 2004-2005
• Finance Committee 2003-2006
• Operating Nuclear Facility Embedded Topical Meeting Program Committee 2003-2004
• Risk Management Embedded Topical Meeting Program Committee 2002-2003
• Nuclear Installations Safety Division Chair 2002-2003
• Business Practices Committee 2001-2003
• PSA '02 (Probabilistic Safety Analysis Topical Meeting) Program Committee 2001-2002
• Low Power/Shutdown PRA Standard Writing Group 1999-2003
• Local Sections Committee Chair 1999-2002
• Planning Committee 1997-2001
• Finance Committee Chair 1993-1996
• Board of Directors 1991-1996
• Executive Committee 1991-1993
• Professional Divisions Committee Chair 1991-1993
• Nuclear Reactor Safety Division Chair 1990-1991
• Education and Training Division Chair 1989-1990
• Symposium on Training Nuclear Facility Personnel Program Committee 1984-1989
• Thermal Reactor Safety Topical Meeting Program Committees (5) 1976-1991
• Nuclear Reactor Safety Division Program Committee 1976-1982
• Executive Assistant to ANS Vice President/President Elect and President 1976-1978
• CT Section Chairman 1975-1976

PUBLICATIONS

W. E. Burchill and B. G. Jones, "The Influence of Axial Conduction on Heat Transfer to Liquid Metals in Reactor Coolant Channels," Trans. ANS 9: 2, 568-569 (1966).

W. E. Burchill, B. G. Jones, and R. P. Stein, "Influence of Axial Heat Diffusion in Liquid Metal - Cooled Ducts With Specified Heat Flux," Trans. ASME C90: 3, 283-290 (1968).

W. E. Burchill, "Analysis of Bowing and Interaction of LMFBR Fuel Subassemblies," Proceedings of the ANS Conference on Fast Reactor Fuel Element Technology, New Orleans, LA, pp. 113-134 (1971).

W. E. Burchill, G. Menzel, R. C. Noyes, and C. F. G. Dupen, "An LMFBR Core Design for Swelling Accommodation," Trans. ANS 14: 2, 714-715 (1971).

W. E. Burchill and B. G. Jones, "Interpretation of Hot-Film Anemometer Response in a Non-Isothermal Field," Proceedings of the Symposium on Turbulence in Liquids, University of Missouri - Rolla, 26-34 (1971).

W. E. Burchill and P. A. Lowe, "Experimental Evaluation of Post- LOCA Steam Relief," Trans. ANS 15: 2, 830-831 (1972).

P. A. Lowe, W. E. Burchill, and J. R. Brodrick, "Experimental Evaluation of Post-LOCA Steam Venting," Proceedings of the ANS Topical Meeting on Water-Reactor Safety, CONF-730304, 196-211 (1973).

J. R. Brodrick, P. A. Lowe, and W. E. Burchill, "Scaling Considerations of Experimental Post-LOCA Steam Relief," Nuclear Technology 24: 2, 137-148 (1974).

R. R. Lee, W. E. Burchill, P. E. Rohan, and S. A. Dunn, "Physics Model for ATWS," Trans. ANS 24: 435 (1976).

W. E. Burchill, Program Manager, "Requirements for Analysis of Transient Fuel Rod Behavior During Design Basis Events," EPRI NP-1022 (1979).

W. E. Burchill, "C-E Perspectives on the ATWS Issue," invited paper presented at ANS Winter Meeting, Trans. ANS 33: 655 (1979).

W. E. Burchill, W. R. Corcoran, and J. W. Pfeifer, "C-E Response to TMI Regulatory Requirements," invited paper presented at ANS Annual Meeting, Trans. ANS 34: 596 (1980).

W. E. Burchill, W. R. Corcoran, and J. W. Pfeifer, "C-E Post-TMI Evaluation Program Being Conducted for the C-E Owner's Group," C-E Paper TIS-6542 (1980).

J. K. Gasper and W. E. Burchill, "C-E Operator Emergency Guidance Program," invited paper presented at ANS Annual Meeting, Trans. ANS 38: 468 (1981).

W. E. Burchill, "PWR Small Break LOCA," review paper presented at the Advanced Course of Nuclear Reactor Safety Assessments, Dubrovnik, Yugoslavia, October 5-9, 1981.

W. E. Burchill, "Anticipated Transients Without Scram," review paper presented at the Advanced Course on Nuclear Reactor Safety Assessments, Dubrovnik, Yugoslavia, October 5-9, 1981.

W. E. Burchill "Physical Phenomena of a Small-Break Loss-of-Coolant Accident in a PWR," Nuclear Safety 23: 5, 525-536 (1982).

W. E. Burchill, "Impact of TMI on Combustion Engineering Technical Activities," invited paper published in Progress in Nuclear Energy 10: 267-283 (1982).

W. E. Burchill, "Effects on the Operation of C-E Reactors Caused by TMI," invited paper presented at the 11th Biennial ANS Topical Conference on Reactor Operating Experience, Scottsdale, Arizona, TANSO 44: Supp1.1, 83 (1983).

W. E. Burchill, contributing author of Guidebook to Light Water Reactor Safety Analysis, Hemisphere Publishing Corp. (1985).

W. E. Burchill, "Accreditation of Training Programs," invited paper presented at ANS Winter Meeting, TANSO 50: 152 (1985).

W. E. Burchill, "The Challenges and Opportunities for the Class of 1990: An Industry Perspective," invited paper presented at ANS Annual Meeting, TANSO 52: 12 (1986).

W. E. Burchill, "Degrees for Control Room Operators - Are We Following a Systematic Approach?," invited paper presented at ANS Winter Meeting, TANSO 55: 158 (1987)

J. R. Sherrard and W. E. Burchill, "Simulator Application in a Nuclear Technology Degree Program," Proceedings of the Eighth Symposium on Training of Nuclear Facility Personnel, CONF-890470, VI-B.5.1 (1989).

W. E. Burchill, "Self Assessment at Pennsylvania Power & Light Nuclear," Proceedings of the Executive Conference on the Role of Self Assessment in a Competitive Environment," American Nuclear Society, IN-650045, December 10-13, 1995.

W. E. Burchill, "Quad Cities Fire Risk Assessment," Invited Presentation at Nuclear Regulatory Commission Regulatory Information Conference, Washington, D.C., March 4, 1999.

W. E. Burchill and D. True, "Positioning ComEd to Apply Risk Insights to Competitive Advantage," Invited Presentation at American Power Conference, Chicago, IL, April 7, 1999.

W. E. Burchill and K. Zee, "Quad Cities Fire Risk Assessment," Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, 175-182, August 22-26, 1999.

J. E. Steinmetz, W. E. Burchill, and K. N. Fleming, "Creating Guidelines for a Contemporary Risk Management Program," Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, 1275-1279, August 22-26, 1999.

W. E. Burchill and D. True, "Managing Simultaneous PRA Upgrades," Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, 1280-1283, August 22-26, 1999.

W. E. Burchill, "ANS LPSD PRA Standard," invited paper presented at ANS Annual Meeting, TANSAO 82: 284 (2000)

W. E. Burchill, "Significance Determination Process," invited paper presented at ANS Annual Meeting, TANSAO 84: 297 (2001)

W. E. Burchill, "Applications of PRA in Plant Operations," invited paper presented at ANS Utility Working Conference, Amelia Island, FL, August 5-9, 2001.

W. E. Burchill, "Significance Determination Process - Exelon's Perspective," Invited Presentation at Nuclear Regulatory Commission Regulatory Information Conference, Washington, D.C., March 6, 2002.

W. E. Burchill, "Exelon Experience with and Expectations for Risk Informed Regulation," invited paper presented at International Meeting on Probabilistic Safety Assessment and Management, San Juan, Puerto Rico, June 24-28, 2002.

W. E. Burchill, "Maintenance Rule (a)(4) and Integrated Risk Management," invited paper presented at ANS Utility Working Conference, Amelia Island, FL, August 11-14, 2002.

W. E. Burchill, "Application of Risk Insights at Exelon," Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, 304-310, October 6-9, 2002.

W. E. Burchill, "Standardization of Risk Management Practices at Exelon's Twelve Sites," 577-584, Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, October 6-9, 2002.

W. E. Burchill, K. Zee, Y. H. In, and R. R. Linthicum, "Analysis of Multiple Fire Induced Spurious Operation Events at Braidwood Nuclear Power Station," 588-591, Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, October 6-9, 2002.

W. E. Burchill, "Exelon Risk Assessment to Support Configuration Risk Management," 636-643, Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment, October 6-9, 2002.

W. E. Burchill, "PRA Self-Assessment - Exelon Perspective," invited presentation at NEI Risk-Informed Regulation Forum, San Diego, CA, November 11-12, 2002.

W. E. Burchill, L. Shanley, and J. Mitman, "Risk Assessment and Monitoring Using ORAM-SENTINELTM To Support Configuration Risk Management at Exelon," Procedings of OECD/NEA/CSNI Working Group on Risk Assessment International Workshop on the Development and Use of Risk Monitors, Madrid, Spain, November 18-20, 2002.

W. E. Burchill, “NPP Improvement by Risk Management,” Procedings of ANS Embedded Topical Meeting, “Risk Management … Now More Than Ever,” TANSAO 88: 863 (2003).

L. Shanley, D. E. True, W. E. Burchill, “PARAGONTM – Next Generation Software for Risk-Informed Decision Making,” Procedings of ANS Embedded Topical Meeting, “Risk Management … Now More Than Ever,” TANSAO 88: 921 (2003).

W. E. Burchill, “Setting Standards for NPP Risk Management Practices,” Procedings of ANS Embedded Topical Meeting, “Risk Management … Now More Than Ever,” TANSAO 88: 928 (2003).

W. E. Burchill and R. Flores, “Texas A&M Education Creativity Supported by DOE and Industry,” Invited paper at ANS Winter Meeting, TANSAO 89: 833 (2003).

W. E. Burchill, J. A. Julius, M. Drouin, and K. L. Kiper, “Qualitative Risk Assessment in the ANS LPSD PRA Standard,” Proceedings of ASME 12th International Conference on Nuclear Engineering, April 25-29, 2004.

D. Bley, W. E. Burchill, M. Drouin, J. A. Julius, K. L. Kiper, and W. Stillwell, “Differences Between Full Power Operations and Low Power / Shutdown Operation, and the Implications on the LPSD Standard, Proceedings of International Conference on Probabilistic Safety Assessment and Management, Berlin, Germany, June 14-18, 2004.

Dan Suson, et al including W. E. Burchill, “The Texas Partnership: A Multi-Dimensional NE University Partnership,” TANSAO 91: 1000-1001 (2004)

J. Ford, W. E. Burchill, et al, “A Multi-Dimensional Nuclear Engineering Partnership,” Proceedings of the 2005 American Society for Engineering Education Annual Conference, Portland, OR, June 12-15, 2005.

Kohlhepp, K. D. and W. E. Burchill, “Evaluation of Engineering Judgment Applied to Analytical Human Reliability Analysis (HRA) Methods,” Proceedings of ANS International Topical Meeting on Probabilistic Safety Assessment, September 11-15, 2005.

Kohlhepp, K. D. and W. E. Burchill, “Numerical Comparison Among Analytical Human Reliability (HRA) Methods for Post-Initiator Actions,” Proceedings of ANS International Topical Meeting on Probabilistic Safety Assessment, September 11-15, 2005.

W. E. Burchill, et al, “Development of PRA Qualification Guidance and Curriculum,” Proceedings of ANS International Topical Meeting on Probabilistic Safety Assessment, September 11-15, 2005.

K. L. Kiper, J. A. Julius, and W. E. Burchill, “Issues Related to LPSD Risk Assessments,” Proceedings of ANS International Topical Meeting on Probabilistic Safety Assessment, September 11-15, 2005.

W. E. Burchill, “Nuclear Power Now and In the Future,” Invited presentation, Bulletin of the American Physical Society, Series II, Vol. 51, No. 2, p. 221, April, 2006.

W. E. Burchill, “Managing Risk During Shutdown Operations,” Invited presentation, TANSAO 94: 29 (2006).