kenneth lee peddicord - tamu college of engineeringkenneth lee peddicord director nuclear power...

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KENNETH LEE PEDDICORD

Director

Nuclear Power Institute

Texas Engineering Experiment Station

Professor of Nuclear Engineering

Dwight Look College of Engineering

Texas A&M University

ADDRESS BIRTH DATE

Gateway Building April 5, 1943

Texas A&M University

3475 TAMU

College Station, TX 77843-3475

Tel: 979/845-5802 ELECTRONIC

Cell: 979/229-8971 [email protected]

Fax: 979/845-1273 http://www.nuclearpowerinstitute.org

Nuclear Engineering Office: http://nuclear.tamu.edu

AI Engineering Building Tel: 979/845-4161

3133 TAMU Fax: 979/845-6443

College Station, TX 77843-3133

DEGREES

B.S.M.E., Mechanical Engineering, University of Notre Dame, 1965.

M.S., Nuclear Engineering, University of Illinois, 1967.

Ph.D., Nuclear Engineering, University of Illinois, 1972.

ACADEMIC POSITIONS

Director, Nuclear Power Institute, Texas A&M University/Texas Engineering

Experiment Station, 2007-present.

Director, Texas Engineering Experiment Station, Texas A&M University System,

2007-2009.

Senior Associate Dean for Research, Dwight Look College of Engineering, Texas

A&M University, 2007-2009.

Vice Chancellor for Research and Federal Relations, Texas A&M University

System, 2003-2007.

Associate Vice Chancellor for Federal Relations, Texas A&M University System,

2000-2003.

Associate Director for Educational Outreach, NASA Commercial Space Center for

Engineering, 1999-2000.

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Director, National Emergency Response and Rescue Training Center, Texas

Engineering Extension Service, 1998-2000.

Associate Vice Chancellor for Strategic Programs, Texas A&M University System,

1994-2000.

Deputy Vice Chancellor and Executive Associate Dean of Engineering, Texas

A&M University, 1993-1994.

Deputy Director, Texas Engineering Experiment Station, 1993-1994.

Interim Vice Chancellor for Engineering, Texas A&M University System, 1993.

Interim Director, Texas Engineering Extension Service, Texas A&M University

System, 1992.

Interim Dean, College of Engineering, Texas A&M University, 1991-1993.

Director, Texas Engineering Experiment Station, Texas A&M University System,

1991-1993.

Associate Dean, College of Engineering, Texas A&M University, 1990-1991.

Assistant Director for Research, Texas Engineering Experiment Station,

Texas A&M University System, 1988-1991.

Head, Department of Nuclear Engineering, Texas A&M University, 1985-1988.

Professor of Nuclear Engineering, Texas A&M University, 1983-present.

Associate Professor of Nuclear Engineering, Oregon State University, 1979-1982.

Assistant Professor of Nuclear Engineering, Oregon State University, 1975-1979.

Research Assistant, Nuclear Engineering Program, University of Illinois, 1966-1971.

NON-ACADEMIC POSITIONS

Visiting Scientist, EURATOM Joint Research Centre-Ispra Establishment, Ispra,

Italy, 1981-82.

Research Nuclear Engineer, Swiss Federal Institute for Reactor Research,

Würenlingen, Switzerland, 1972-1975.

CONSULTING POSITIONS

Longnecker and Associates, 2009-2010.

TechSource, Inc., 2007-2009.

Idaho National Laboratory, 2009-2014.

Pacific Northwest National Laboratories, 2002-2013.

U.S. Department of Energy, Idaho Operations Office, Idaho Falls, ID, Generation

IV Roadmap, 2001-2003.

Nuclear Regulatory Commission, Phenomena Identification and Ranking Team,

Washington, D.C., 1999-2001.

National Science Foundation IGERT Panel, Washington, D.C., 1998.

Lawrence Livermore National Laboratory, Livermore, CA, 1998-present.

Arkansas Department of Higher Education, Little Rock, AR, 1990.

Universities Space Research Association, Houston, TX, 1989-1997.

Argonne National Laboratory, Argonne, IL and Idaho Falls, ID, 1989, 2000-

2001.

Pennsylvania Power & Light, Allentown, PA, 1986.

Los Alamos National Laboratory, Los Alamos, NM, 1984-1989, 2002-present.

Battelle Human Affairs Research Center, Bellevue, VA, 1984.

Portland General Electric Company, Portland, OR, 1980.

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EG&G Idaho, Inc., Idaho Falls, ID, 1979.

FIELDS OF SPECIALIZATION

Human resource development for the nuclear industry.

Behavior of nuclear fuels, disposition of weapons plutonium, space nuclear power

systems and missions.

International engineering education and curriculum policy.

Generation IV nuclear energy systems.

Nuclear generated hydrogen and the hydrogen economy.

PROFESSIONAL ACTIVITIES

Professional Societies

American Nuclear Society

American Society for Engineering Education

American Society of Mechanical Engineers

Professional Registration

Registered as a Professional Engineer, State of Texas, Registration No.

55073.

Professional Recognition

Glen Murphy Award, American Society for Engineering Education, 2002.

Fellow, American Nuclear Society, 2002.

Keynote Speaker, Joint Meeting of the Mexican Nuclear Society and the Mexican Society

for Radiation Protection, Morelia, Mexico, September 18, 2000.

Invited Speaker, Belgian Nuclear Society, Addressing Weapons

Plutonium Disposition, Brussels, Belgium, May 14, 1998.

Key Speaker, NATO Advanced Research Workshop on Safety Issues for

Plutonium Involvement in the Nuclear Fuel Cycle, Moscow,

Russia, September 1-6, 1997.

Commencement Speaker, Amarillo Prep Program, Amarillo, Texas, July

25, 1997.

North Atlantic Treaty Organization, Key Speaker on NATO Science

Programs in Disarmament, NATO High Level Review Group,

Brussels, Belgium, June 6, 1997.

Key Speaker, NATO Advanced Research Workshop on Nuclear Materials

Safety Management, Amarillo, Texas, March 17-21, 1997.

Keynote Speaker, National Student Leadership Conference, Salt Lake City,

Utah, October 26, 1995.

Texas A&M University Multicultural Diversity Award for Administration,

1995.

University of Notre Dame, College of Engineering Honor Award for

Significant Contributions to the Advancement of Engineering, 1994.

Educador Internácional, Universidad Autónoma de Tamaulipas, Ciudad

Victoria, Tamaulipas, Mexico, 1993.

American Nuclear Society Materials Science and Technology Division

Chairman's Award, 1989.

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Keynote Speaker, International Atomic Energy Agency Workshop on Light

Water Reactor Fuel Performance, Preston, England, September 9,

1987.

Keynote Speaker, 5th International Seminar on Mathematical/ Mechanical

Modeling of Reactor Fuel Elements, Harwell, England, August 15-

16, 1985.

Texas Engineering Experiment Station Research Fellow, 1984-85.

Best Paper Award, AIAA 9th Annual Technical Symposium, Johnson

Space Center, 1984.

Listed in International Who's Who in Engineering, 1983.

Certificate of Governance, American Nuclear Society, 1983, 84, 85.

Alpha Nu Sigma National Nuclear Engineering Honorary Society, 1982.

Listed in Who's Who in Technology Today, 1980.

Listed in Outstanding Young Men of America, 1980.

OSU Faculty Development Award, 1978.

Oregon State University Lloyd Carter Award for Outstanding and

Inspirational Teaching, School of Engineering, 1978.

Danforth Associate, Danforth Foundation, 1978-1984.

Pi Tau Sigma National Mechanical Engineering Honorary Fraternity, 1965.

Committees, Commissions, and Boards

U.S. Department of Commerce Civil Nuclear Trade Advisory Committee

(CINTAC), Member, 2015-present.

U.S. Nuclear Waste Technical Review Board, Board Member, 2012-

present.

International Subcommittee, Nuclear Energy Advisory Committee, Office

of Nuclear Energy, U.S. Department of Energy, 2011-present.

Directorate Review Committee, Energy Science and Technology

Directorate, Battelle Pacific Northwest National Laboratory, 2007-

2011.

Research Commission, Department of Nuclear Energy and Safety, Paul

Scherrer, 2009-2012.

Los Alamos National Security, LLC and Lawrence Livermore National

Security, LLC Board of Governors Science and Technology

Committee, 2009-present.

Texas Low Level Radioactive Waste Compact Disposal Commission,

Member, 2009-2011.

Idaho National Laboratory Advanced Test Reactor National Scientific Users

Facility Scientific Review Board, 2009-2014.

Landau Network Centro Volta International Working Group, 2006-2009

Scientific Advisory Committee, Laboratory for Reactor Physics and

Systems Behaviour, Paul Scherrer Institut, Chair, 2003-2012.

Blue Ribbon Panel on Proliferation Resistant Characteristics of Recycle

Fuels, 2002-2003.

Directorate Review Committee, Energy and Environment Directorate,

Lawrence Livermore National Laboratory, 2000-2006, Chair, 2005-

2006.

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Division Review Committee, Nuclear Materials Technology Division, Los

Alamos National Laboratory, 2000-2005, Chair, 2004-2005.

International Coordinating Committee, Youth and the Plutonium Challenge,

1998-2000.

Head, Educational Programs, Eagle Alliance, 1998-2000.

Amarillo National Resource Center for Plutonium, Governing Board, 1995-

2001.

Pacific University Alliance, Director, 1995-1996.

Universities Space Research Association, Council for Science and

Engineering Education, 1989-1997.

National Research Council Committee on Advanced Space Based High

Power Technologies, 1987-88.

NASA OAET Aerospace Research and Technology Subcommittee

(Power), 1987-89.

SP-100 Materials Science Review Committee, DARPA/NASA/DOE,

1984-86.

American Nuclear Society, Materials Science and Technology Division

Executive Committee, 1983-86; Secretary-Treasurer, 1985-86; Vice

Chair/Chair Elect, 1986-87; Chair, 1987-88.

American Nuclear Society, Board of Directors, 1988-91.

Nuclear Engineering Department Heads Organization, Secretary-Chair

Elect, 1987-88; Chair, 1988-89.

Advisory Editorial Board for Nuclear Science and Engineering, 1984-86.

Technical Program Committee, International Conference on Reliable Fuels

for Liquid Metal Reactors, 1985-86.

American Nuclear Society, Student Activities Committee, 1976-1985;

Chair, 1978-1981.

N.E.E.D. Committee (Nuclear Engineering Education for the

Disadvantaged); 1978-92; Secretary, 1978-80; Vice Chair, 1985-88;

Chair, 1988-1991.

John and Muriel Landis Scholarship Committee, 1979-1992; Chair, 1985-

1991.

American Nuclear Society, Education Division Executive Committee,1979-

1982; Secretary- Treasurer, 1982-83; Vice Chair/Chair Elect, 1983-

84; Chair, 1984-85.

American Nuclear Society, Oregon Section, Board of Directors, 1977.

American Nuclear Society, Oregon Section, Education Committee, 1976,

1979, 1980.

Academic Service

Texas A&M University Committee on Science and Technology Policy,

George Bush School of Government and Public Service, 1997-

1999.

Texas A&M University System Research and Federal Council, 1994-1996.

Society for Mexican-American Engineers and Scientists, TAMU Chapter,

Co-Advisor, 1993-2008.

INDAR Director Search Advisory Committee, Chair, TEES, 1991.

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Texas A&M Research Foundation Users' Council, 1989-1993.

Texas A&M University Council of Principal Investigators, 1987-1991.

Texas Transportation Institute Research Council, 1987-1993.

Mechanical Engineering Department Head Search Advisory Committee,

Chair, Texas A&M University, 1989.

Chemical Engineering Department Head Search Advisory Committee,

Chair, Texas A&M University, 1986-87.

Texas A&M University Reactor Safety Board, 1986-88.

Texas A&M University Faculty Development Leave Committee, 1985-88.

American Nuclear Society, TAMU Student Chapter, Faculty Advisor,

1983-1987, 1998-present.

Alpha Nu Sigma Nuclear Engineering Honorary Fraternity, OSU Faculty

Advisor, 1981-82.

American Nuclear Society, OSU Student Chapter, Faculty Advisor, 1976-

81.

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PUBLICATIONS

Books, Journals, Transactions, Proceedings, and Abstracts

K. L. Peddicord, Tami Davis Hollar, John Poston, Paulo Barretto, Valerie Segovia, R.

Cable Kurwitz, W. Wayne Kinnison, Galina Tsvetkov, Natela Ostrovskaya and

Jonee Haines, Nuclear Power Institute, Texas A&M University and the Texas

A&M Engineering Experiment Station, Rudolph Henry, Wharton County Junior

College, and Linda Morris, Texas State Technical College Waco, “The Nuclear

Power Institute Programs for Human Resource Development for the Nuclear

Industry,” Invited Keynote Presentation, IAEA International Conference on

Human Resource Development for Nuclear Power Programmes, Vienna, Austria,

May 12-16, 2014.

K. L. Peddicord, “Coordination of University, Vocational School, High School and

Industry: Education and Training for Nuclear Power,” International Conference

on Human Resource Development for Introducing and Expanding Nuclear

Power Programmes, Abu Dhabi, United Arab Emirates, March 16-19, 2010.

P. V. Tsvetkov, K. Vierow, K. L. Peddicord, J. C. Ragusa, S. M. McDeavitt, J. W.

Poston, Sr., L. Shao, and G. Willems, "Autonomous Multi-purpose Floating

Power System with a Compact Static Pebble Bed Reactor," PHYSOR ‘08 –

International Conference on the Physics of Reactors, Interlaken, Switzerland,

September 14-19, 2008.

W. Charlton, K. L. Peddicord, N. Geraskin, E. Kryuchkov, V. Bolyatko, I. A. Vorobieva,

and D. Klinov, "Analysis of New Challenges in Non-Proliferation Education,"

PHYSOR 2008 International Conference on the Physics of Reactors, Interlaken,

Switzerland, September 14-19, 2008.

K. L. Peddicord, “The Global Nuclear Energy Partnership and the Global Nuclear Power

Infrastructure Initiatives”, Landau Network Centro Volta, Como, Italy, January,

2007.

K. L. Peddicord, “Nuclear Generated Hydrogen—Near Term Opportunities for

Utilization”, Scientific Forum, International Atomic Energy Agency, Vienna,

Austria, September, 2004.

David C. Wade, et al, “STAR-H2, A 400 MWth Lead-Cooled, Long Refueling Interval

Reactor with Hydrogen Production”, ICONE 11, Tokyo, Japan, April 20-23, 2003.

K. L. Peddicord and Yury Kazansky, Benmarking Requirements for Facilities in the

Nuclear Fuel Cycle, NATO ASI Series, Kluwer Publishing Company, Dordrecht,

The Netherlands (2003).

K. L. Peddicord, Yury Kazansky and Paul Govaerts, Decommissioning, Decontamination,

Disassembly and Dismantlement of Facilities in the Nuclear Fuel Cycle, NATO

ASI Series, Kluwer Publishing Company, Dordrecht, The Netherlands (2003).

G. V. Tsvetkova, K. L. Peddicord. “Utilization of Plutonium and Higher Actinides in the

HTGR as Possibility to Maintain Long-Term Operation on One Fuel Loading”,

10th International Conference on Nuclear Engineering (ICONE 10), "Nuclear

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Energy - Engineering Today, the Power for Tomorrow", Arlington, Virginia, USA,

Track 6-Next Generation Systems, April 14-18, 2002.

S. Reynaud and K. L. Peddicord, “Re-assessment of Nitride Fuel Potential in the Current

Context of the Nuclear Industry", 10th International Conference on Nuclear

Engineering (ICONE 10), "Nuclear Energy - Engineering Today, the Power for

Tomorrow", Arlington, Virginia, USA, April 14-18, 2002.

D. C. Wade, R. Doctor and K. L. Peddicord, “STAR-H2: The Secure Transportable

Autonomous Reactor for Hydrogen Production and Desalination", 10th

International Conference on Nuclear Engineering (ICONE 10), "Nuclear Energy -

Engineering Today, the Power for Tomorrow", Arlington, Virginia, USA, April 14-

18, 2002.

Charles W. Forsberg and K. L. Peddicord, “Why Hydrogen Production from Nuclear

Power?”, Spring National Meeting, American Institute of Chemical Engineers, New

Orleans, LA (February, 2002).

B. E. Boyack, et al., “Phenomenon Identification and Ranking Tables (PIRTs) for Rod

Ejection Accidents in Pressurized Water Reactors Containing High Burnup Fuel”,

NUREG/CR-6742 (2001).

B. E. Boyack, et al., “Phenomenon Identification and Ranking Tables (PIRTs) for Power

Oscillations Without Scram in Boiling Water Reactors Containing High Burnup

Fuel”, NUREG/CR-6743 (2001).

B. E. Boyack, et al., “Phenomenon Identification and Ranking Tables (PIRTs) for Loss-of-

Coolant Accidents in Pressurized and Boiling Water Reactors Containing High

Burnup Fuel”, NUREG/CR-6744 (2001).

C. W. Forsberg and K. L. Peddicord, “Hydrogen Production as a Major Nuclear Energy

Application”, Nuclear News, 44, No. 10, pg 41 (2001).

G. V. Tsvetkova, K. L. Peddicord, D.R. Liles, T.D. Knight, and J.P. Nelson, “Concept

Analysis of a Modular 50 MWth, Pebble Bed High-Temperature Gas-Cooled

Reactor for Process Heat. Los Alamos National Laboratory, LA-UR-01-5161,

USA, (October, 2001).

G. V. Tsvetkova and K. L. Peddicord. “A Long-Term Energy Source Based on an HTGR

Concept”, Trans.Am.Nucl.Soc., 84, 115 - 116, (2001).

P. G. Medvedev and K. L. Peddicord, “Analyzing the Thermo Mechanical Behavior of

LEU and Weapons Grade MOX Fuel Pins in WWER-1000 Using the COMETHE-

4D and Frapcon-3 Fuel Performance Codes”, Trans.Am.Nucl.Soc., (2000).

John M. Alvis, Philippe M. Bellanger, Pavel G. Medvedev, K. L. Peddicord, “Evaluations

of Weapons Grade MOX Fuel Performance Using the COMETHE Computer

Code”, American Nuclear Society International Topical Meeting on Light Water

Reactor Fuel Performance, Park City, Utah, April 10-13, 2000.

A. E. Waltar, K. L. Peddicord and P. Nelson, “Will the Nuclear Production of Hydrogen

Be Socially Acceptable?” The First Information Exchange Meeting on Nuclear

Production of Hydrogen, OECD Nuclear Energy Agency, Paris, France, October 2-

3, 2000.

B. W. Spencer, R. D. Doctor, D. C. Wade, K. L. Peddicord, C. Boardman, and G.

Marucci, “A Proposed Modular-Sized, Integrated Nuclear and Hydrogen-Based

Energy Supply/Carrier System,” The First Information Exchange Meeting on

Nuclear Production of Hydrogen, OECD Nuclear Energy Agency, Paris, France,

October 2-3, 2000.

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Yury Kazansky, Irina Vorobyova and K. L. Peddicord, "Educational Programs to Prepare

Graduates for Decommissiong and Dismantlement of Facilities in the Nuclear Fuel

Cycle," NATO Advanced Research Workshop on the Decommissioning,

Decontamination, Disassembly and Dismantlement of Facilities in the Nuclear Fuel

Cycle, Obninsk, Russia, August 20-23, 2000.

K. L. Peddicord, Leslie J. Jardine, Leonard Lazarev, V. V. Khromov, Yury Kazansky,

Terry Lash, Douglas Newton, Edward Kryuchkov, Victor Bolyatko, Paul Nelson,

Max Roundhill, Bill Harris, Mikhail Moshkov, Irina Vorobyova, “Nuclear

Materials Facilities Safety Initiative,” Kazakhstan Nuclear Power Technologies-

2000, Astana City, Kazakhstan, May 14-17, 2000. K. L. Peddicord, P. M. Bellanger and P. G. Medvedev, “Comparative Calculations of

Thermo-Mechanical Behavior of LEU and WGMOX Fuel Pins in Light Water

Reactors Using COMETHE-4D and FRAPCON-3 Steady State Fuel Performance

Codes,” Kazakhstan Nuclear Power Technologies-2000, Astana City, Kazakhstan,

May 14-17, 2000.

J. M. Alvis, P. M. Bellanger, P. G. Medvedev and K. L. Peddicord, “Evaluation of the

Weapons Grade MOX Fuel Performance Using the COMETHE Computer Code,”

American Nuclear Society International Topical Meeting on Light Water Reactor

Fuel Performance, Park City, Utah, April 10-13, 2000.

P. Bellanger, P. Medvedev, J. Alvis and K. L. Peddicord, “Evaluation of Weapons Grade

MOX Fuel Performance in Light Water Reactors Using the COMETHE Computer

Code,” International Conference on Future Nuclear Systems, GLOBAL ’99,

Jackson Hole, Wyoming, August 29-September 3, 1999.

L.J. Jardine, K.L. Peddicord, F.E. Witmer, P.F. Krumpe, L. Lazarev, and M. Moshkov,

“Reducing Nuclear Danger through Intergovernmental Technical Exchanges on

Nuclear Materials Safety Management,” Journal of Radioanalytical and Nuclear

Chemistry, Vol. 235, Nos. 1-2, p 125-127, Elsevier Science B.V., Amsterdam

(1998).

Fred E. Witmer, Paul F. Krumpe, David D. Carlson, Mary L. Young, M. Lee Hyder,

Leslie J. Jardine, K. L. Peddicord, Leonard N. Lazarev, Victor N. Dushin, Mikhail

M. Moshkov, Boris F. Petrov, Valeriy N. Romanovskiy, “Russian-U.S. Joint

Program on the Safe Management of Nuclear Materials, ,” Spectrum ’98,

International Conference on Decommissioning and Decontamination and on

Nuclear and Hazardous Waste Management, Denver, Colorado, September 13-18,

1998.

Christopher C. Allison, K.L. Peddicord, Sean O'Kelly, Amy B. Caldwell, “Simulation Of

MOX Fuel Thermal Gradients To Study Gallium Interactions,” Third Topical

Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management,

Charleston, SC, September 9-11, 1998.

K. L. Peddicord, John Alvis, Pavel Medvedev, Phillipe Belanger, and Gregory I. Gellene,

“Modeling the Performance of Weapons MOX Fuel in Light Water Reactors,”

Amarillo National Resource Center for Plutonium 1998 Researchers Conference,

Amarillo, Texas, July 21-22, 1998.

K. L. Peddicord, et al., “The US-Russian Nuclear Materials Safety Activity and

Opportunities for University Collaboration,” Youth and the Plutonium Challenge

Conference, Obninsk, Kaluga Region, Russian Federation, July 5-10, 1998.

10

K. L. Peddicord, “Summary of Nuclear Materials Safety ARW in Amarillo and

Relationship to this ARW,” NATO Advanced Research Workshop on Nuclear

Materials Safety II, St. Petersburg, Russian Federation, June 8-10, 1998.

K. L. Peddicord, et al, “Nuclear Materials Safety Activity--The University-to-University

Component,” NATO Advanced Research Workshop on Nuclear Materials Safety

II, St. Petersburg, Russian Federation, June 8-10, 1998.

V. V. Khromov, et al, “New Academic Program Development Relating to Nuclear

Materials Safety,” NATO Advanced Research Workshop on Nuclear Materials

Safety II, St. Petersburg, Russian Federation, June 8-10, 1998.

Paul Nelson, et al, “University Contributions to Research in Nuclear Materials Safety,”

NATO Advanced Research Workshop on Nuclear Materials Safety II, St.

Petersburg, Russian Federation, June 8-10, 1998.

K. L. Peddicord, Leonard Lazarev and Leslie J. Jardine, Nuclear Materials Safety

Management, NATO ASI Series, ISBN 0-7923-5191-6, Kluwer Publishing

Company, Dordrecht, The Netherlands (1998).

K. L. Peddicord and John Alvis, “Performance Modeling for Weapons MOX Fuel in Light

Water Reactors,” NATO Advanced Research Workshop on Safety Issues

Associated with Plutonium Involvement in Nuclear Fuel Cycles, Moscow, Russian

Federation, September 1-5, 1997.

L. J. Jardine, K. L. Peddicord, F. E. Witmer, P. F. Krumpe, L. Lazarev and M. Moshkov,

“Reducing Nuclear Danger through Intergovernmental Technical Exchanges on

Nuclear Materials Safety Management,”, International Topical Conference on

Methods and Applications of Radioanalytical Chemistry-IV, Kona, Hawaii, April

9-12, 1997.

John Graham and Kenneth L. Peddicord, “The Pacific University Alliance,” Pacfic Basin

Nuclear Conference, Kobe, Japan, October 20-24, 1996.

R. E. Ewing and K. L. Peddicord, “Supercomputing for Texas and Mexico,” Proceedings,

Sixth Annual Mexico-Texas Higher Education Conference, Texas A&M

University-Kingsville, Kingsville, Texas, April 7-9, 1994.

F. O. Onbasioglu, A. G. Parlos, K. L. Peddicord and J. D. Metzger, “Gain -Scheduled

Controller Design for Load-Following in Static Space Nuclear Power Systems,”

Transactions of the 11th Symposium on Space Nuclear Power and Propulsion

Systems, Albuquerque, NM, January 10-14, 1994.

David J. Senor, Kenneth L. Peddicord, and L. R. Cornwell, “High Fiber Volume Fraction

Metal Matrix Composites Cast Under Bi-Dimensional Compression,” Journal of

Composite Materials, Vol. 27, No. 12, 1312-1325 (1993).

Steven L. Hayes and Kenneth L. Peddicord, “Radiative Heat Transfer in Porous Uranium

Dioxide”, Journal of Nuclear Materials, Vol. 202, 87-97 (1993).

S. L. Hayes and K. L. Peddicord, "Numerical Analysis of Radiative Heat Transfer in

Porous Uranium Dioxide," Winter Annual Meeting, American Society of

Mechanical Engineers, Anaheim, CA, November 8-13, 1992.

K. L. Peddicord, "How to Attract and Reward Design Faculty," Annual Meeting of the

American Society for Engineering Education, Toledo, OH, June 16-19, 1992.

David J. Senor, Kenneth L. Peddicord, and James P. Strizak, "Effects of Hydrogen on the

Fracture Morphology of Inconel 718," Materials Letters, Vol. 11, Nos. 10, 11, 12,

373-378 (1991).

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A. G. Parlos, E. U. Khan, K. Kent, and K. L. Peddicord, “Advanced Thermionic Reactors

for Surface Nuclear Power Applications,” AIAA/NASA/OAI Conference on

Advanced SEI Technologies, AIAA Paper No. AIAA 91-3465, Cleveland, OH,

September, 1991.

Wesley E. Bolch, James Kelly Thomas, and K. L. Peddicord, "Radiation Protection

Considerations in Space Station Missions," Trans.Am.Nucl.Soc., 64, 458 (1991).

K. L. Peddicord, "Contributions of University Nuclear Engineering Departments to the

National Research Agenda", Trans.Am.Nucl.Soc., 64, 58 (1991).

John M. Alvis, James Kelly Thomas, and K. L. Peddicord, "Cermet Fuel Thermal

Conductivity," Trans. Am.Nucl.Soc., 64, 269 (1991).

A. G. Parlos, R. Frymire, S. B. Negron, J. K. Thomas, K. L. Peddicord, and E. U. Khan,

"A Preliminary Feasibility Study of Passive In-Core Thermionic Reactors for

Highly Compact Space Nuclear Power Systems," Transactions of the 8th

Symposium on Space Nuclear Power Systems, Albuquerque, NM, January 6-10,

1991.

Robert O. Montgomery, et al., "Validation of FREY for the Safety Analysis of LWR Fuel

using Transient Fuel Rod Experiments," Nuclear Engineering and Design, Vol.

121, 395-408 (1990).

Steven L. Hayes, James Kelly Thomas, and Kenneth L. Peddicord, "Development of a

Creep Rate Porosity Correction Factor," Materials Letters, Vol. 9, No. 2, 435-442

(1990).

Steven L. Hayes, James Kelly Thomas, and Kenneth L. Peddicord, "Material Properties of

Uranium Mononitride: Part I. Physical Properties," Journal of Nuclear Materials,

Vol. 171, 262-270 (1990).


Uranium Mononitride: Part II. Mechanical Properties," Journal of Nuclear

Materials, Vol. 171, 271-288 (1990).


Uranium Mononitride: Part III. Transport Properties," Journal of Nuclear

Materials, Vol. 171, 289-299 (1990).


Uranium Mononitride: Part IV. Thermodynamic Properties," Journal of Nuclear

Materials, Vol. 171, 300-318 (1990).

David J. Senor, James Kelly Thomas, and Kenneth L. Peddicord, "Thermophysical

Property Correlations for the Niobium-1% Zirconium Alloy", Journal of Nuclear

Materials, Vol. 173, 261-273 (1990).

David J. Senor, James Kelly Thomas, and Kenneth L. Peddicord, "Transport Property

Correlations for the Niobium-1% Zirconium Alloy", Journal of Nuclear Materials,

Vol. 173, 274-283 (1990).

A. G. Parlos, E. U. Khan, R. Frymire, S. Negron, J. K. Thomas, and K. L. Peddicord, "A

Passive In-Core Thermionics Reactor for Highly Compact Space Nuclear Power

Systems," 25th Intersociety Energy Conversion Engineering Conference, Reno,

NV, August 12-17, 1990.

W. E. Bolch, J. K. Thomas, K. L. Peddicord, S. M. Stevenson, and A. J. Willoughby, "A

Radiation Protection to Space Nuclear Power Operations," Transactions of the

Health Physics Society Annual Meeting, Anaheim, CA, June 24-28, 1990.

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J. K. Thomas and K. L. Peddicord, "The Activated Heat Source (AHS) Concept: Scoping

Analysis," Transactions of the 7th Symposium on Space Nuclear Power Systems,

Albuquerque, NM, January 7-11, 1990.

D. J. Senor, J. K. Thomas, and K. L. Peddicord, "Material Property Correlations for

Niobium-1% Zirconium Alloy," Transactions of the 7th Symposium on Space

Nuclear Power Systems, Albuquerque, NM, January 7-11, 1990.

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Material Property Correlations for

Uranium Mononitride," Transactions of the 7th Symposium on Space Nuclear

Power Systems, Albuquerque, NM, January 7-11, 1990.

W. E. Bolch, J. K. Thomas, K. L. Peddicord, S. M. Stevenson, and A. Willoughby, "A

Radiological Assessment of Space Nuclear Power Operations near Space Station

Freedom," Transactions of the 7th Symposium on Space Nuclear Power Systems,


James Kelly Thomas, Kenneth L. Peddicord, Robert O. Montgomery, Dion J. Sunderland,

and William F. Lyon, III, "Nuclear Power Applications for Lunar and Cislunar

Missions," Lunar Bases and Space Activities of the 21st Century, Volume 2, ed. W.

W. Mendell, editor, Lunar and Planetary Institute, Houston, TX (1989).

A. David Rossin, KunMo Chung, and Kenneth L. Peddicord, "Executive Summary:

Research in Nuclear Power - Workshop on the Needs of the Next Generation of

Nuclear Power Technology", Nuclear Technology, Vol. 88, No. 2, 107 (1989).

D. J. Senor, J. K. Thomas, and K. L. Peddicord, "Tensile Property Behavior of the

Niobium-1% Zirconium Alloy, " Abstracts of the 1989 Fall Meeting of the

Metallurgical Society, Indianapolis, IN, October 1-5, 1989.

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "A Steady State Creep Rate Correlation

for Uranium Mononitride," Abstracts of the 91st Meeting of the American Ceramic

Society, p. 385, Indianapolis, IN, April 24-26, 1989.

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Development of a Porosity Correction

Factor for Creep Rate," Abstracts of the 91st Meeting of the American Ceramic

Society, p. 209, Indianapolis, IN, April 24-26, 1989.

J. M. Alvis, J. K. Thomas, and K. L. Peddicord, "Cermet Fuel Thermal Conductivity, "

Abstracts of the 91st Meeting of the American Ceramic Society, p. 386,

Indianapolis, IN, April 24-26, 1989.

D. J. Senor, J. K. Thomas, and K. L. Peddicord, "Niobium-1% Zirconium Property

Correlations for Electrical Resistivity, Thermal Conductivity, Thermal Expansion,

Specific Heat, and Hemispherical Total Emittance," Transactions of the 6th

Symposium on Space Nuclear Power Systems, p. 205, Albuquerque, NM, January

8-12, 1989.

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Elastic Constants and Creep of Uranium

Mononitride," Transactions of the 6th Symposium on Space Nuclear Power

Systems, p. 417, Albuquerque, NM, January 8-12, 1989.

J. K. Thomas, D. E. Brozak, and K. L. Peddicord, "Irradiation Performance Correlations

for Nitride Fuels," Abstracts of the American Ceramic Society, 90th Annual

Meeting, p. 237, Cincinnati, OH, May 1-5, 1988.

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Mechanical Properties of Uranium

Nitride," Abstracts of the American Ceramic Society, 90th Annual Meeting, p. 237,

Cincinnati, OH, May 1-5, 1988.

13

J. K. Thomas, K. L. Peddicord, S. H. Lowy, and G. K. Bennett, "Nuclear Power

Applications for Lunar and Cislunar Missions," 2nd Symposium on Lunar Bases

and Space Activities of the 21st Century, Houston, TX, April 5-7, 1988.

D. E. Brozak, J. K. Thomas, and K. L. Peddicord, "An Irradiation Performance Data Base

for Nitride Fuels, Transactions of the 5th Symposium on Space Nuclear Power


J. K. Thomas, D. E. Brozak, S. L. Hayes, and K. L. Peddicord, "Material Property and

Irradiation Performance Correlations for Nitride Fuels," Transactions of the 5th

Symposium on Space Nuclear Power Systems, p. 535, Albuquerque, NM, January

11-14, 1988.

Kenneth L. Peddicord et al., "Effective Thermal conductivity in Multi-Fraction Reactor

Fuels, Journal of Nuclear Science and Technology, Vol. 24, No. 9, pp. 667-683,

(1987).

Kenneth L. Peddicord and Curtis V. De Vore "Current Trends in Fuel Development and

Future Needs in Extended Burnup," Nuclear Engineering and Design, Vol. 101,

199 (1987).

Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer and Charles R. Albury,

"Nodalization Study of the Westinghouse Model E Steam Generator Secondary

Side," Nuclear Technology, Vol. 76, No. 1, 126-136 (1987).

George P. Peterson, Leroy S. Fletcher and Kenneth L. Peddicord, “Thermal Conductivity

in Sphere Pac Reactor Fuels,” Journal of Nuclear Science and Technology, Vol.

24, No. 9, pp. 1-7 (1987).

E. W. Bechler, R. O. Montgomery, K. L. Peddicord, "The Assessment of FREY's

Capabilities for Steady-State Self-Initialization," Trans.Am.Nucl.Soc., 55, 293

(1987).

D. E. Brozak, J. K. Thomas, K. L. Peddicord, "A Nitride Fuels Irradiation Performance

Data Base," Trans.Am.Nucl.Soc., 55, 296 (1987).

M. E. Portal, K. L. Peddicord, "Creep Measurements for Low-Melting-Point Metals,"

Trans.Am.Nucl.Soc., 55, 300 (1987).

W. F. Lyon, Y. A. Hassan, K. L. Peddicord, "The Simulation of Thermal Mixing in Main

Steam Generator Feedlines," Trans.Am.Nucl.Soc., 55, 737 (1987).

W.F. Lyon, R. O. Montgomery, J. K. Thomas, and K. L. Peddicord, "A Fully Passive

Space Reactor," Trans.Am.Nucl.Soc., 54, 5 (1987).

W. F. Lyon, III, J. A. George, J. W. Alred, and K. L. Peddicord, "NASA Universities

Advanced Space Design Program, Focus on Nuclear Engineering,"

Trans.Am.Nucl.Soc., 54, 5 (1987).

D. E. Brozak, J. K. Thomas, K. L. Peddicord, and E. W. Bechler, "A Nitride Fuels Data

Base," Abstracts of the American Ceramic Society, 89th Annual Meeting, p. 279,

Pittsburgh, PA, April 26-30, 1987.

J. M. Alvis, J. K. Thomas, and K. L. Peddicord, "Irradiation Behavior of Cermet Fuels,"

Abstracts of the American Ceramic Society, 89th Annual Meeting, p. 287,

Pittsburgh, PA, April 26-30, 1987.

J. K. Thomas, W. F. Lyon, III, R. O. Montgomery and K. L. Peddicord, "The Fully Passive

Space Reactor Concept: A Scoping Study," Abstracts of the AIAA 12th Annual

Technical Symposium, May 14, Houston, TX (1987).

14

D. J. Sunderland and K. L. Peddicord, "Considerations On Nuclear (Fission) Space

Propulsion," Abstracts of the AIAA 12th Annual Technical Symposium, May 14,

Houston, TX (1987).

G. P. Peterson, L. S. Fletcher, and K. L. Peddicord, "Thermal Conductivity in Multi-

Fraction Fuels," Proceedings of the ASME/JSME Thermal Engineering Joint

Conference, Honolulu, Hawaii, March 22-27, 1987

J. M. Alvis, J. K. Thomas, and K. L. Peddicord, "Cermet Fuel Conductivity,"

Transactions of the 4th Symposium on Space Nuclear Power Systems, p. 323,


D. J. Sunderland and K. L. Peddicord, "Nuclear Electric Propulsion System: Nuclear Plant

and Thermomechanical Conversion System," Transactions of the 4th Symposium

on Space Nuclear Power Systems, p. 185, Albuquerque, NM, January 12-16, 1987.

W. F. Lyon, III, R. O. Montgomery, J. K. Thomas, and K. L. Peddicord, "Fully Passive

Space Reactor Design Concept," Transactions of the 4th Symposium on Space

Nuclear Power Systems, p. 139, Albuquerque, NM, January 12-16, 1987.

Kenneth L. Peddicord, Richard W. Stratton and James Kelly Thomas, "Analytical and

Experimental Performance of Sphere-Pac Nuclear Fuels," Progress in Nuclear

Energy, Vol. 18, No. 3, 265-299 (1986).

Curtis V. De Vore and Kenneth L. Peddicord, "Potential for Cladding Failure During

Transient Events at Extended Burnups," Nuclear Engineering and Design (1986).

C. V. De Vore and K. L. Peddicord, "Transient Response of Extended Burnup Fuel

Elements," Abstracts of the 88th American Ceramic Society Annual Meeting,

Chicago, IL, April 27-May 1, 1986.

C. V. De Vore and K. L. Peddicord, "Performance of Ceramic UO2 Fuels Under Extended

Burnup Conditions," Proceedings of the World Congress on High Tech Ceramics,

Milan, Italy, June 22-25, 1986.

J. K. Thomas and K. L. Peddicord, "Mechanical Behavior of Sphere Pac Nuclear Fuel,"

Transactions of ENC'86/ENC 4/FORATOM IX, 4, p. 325, Geneva, Switzerland,

June 1-6, 1986.

K. L. Peddicord, D. L. Eubanks, and J. A. George, "Optimization of Uranium Nitride Fuel

Designs for SP-100," Transactions of the 3rd Symposium on Space Nuclear Power


Thomas L. George, Timothy C. Kennedy and Kenneth L. Peddicord, "An Elastic Stress-

Strain Relation for Sphere Arrays Undergoing Initial Stage Sintering," Transactions

of the American Society of Mechanical Engineers, Journal of Applied Mechanics,

Vol. 52, 97-104 (1985).

Thomas L. George, Timothy C. Kennedy and Kenneth L. Peddicord, "An Elastic Stress-

Strain Relation for Sphere Arrays Undergoing Initial Stage Sintering," Transactions

of the American Society of Mechanical Engineers, Journal of Applied Mechanics,

Vol. 52 98-104 (1985).

K. L. Peddicord, "Nuclear Fuels and Materials at Texas A&M--Fissile, Fertile, and Futile,"

Trans. Am.Nucl.Soc., 50, 63 (1985).

L. Kachnik, V. Scharrer, V. Djordjevic, F. R. Best, and K. L. Peddicord, "Characteristics

of Solid/Liquid Flow in a 2 in. Pipe," Trans.Am.Nucl.Soc., 50, 109 (1985).

R. O. Montgomery, C. V. De Vore, and K. L. Peddicord, "Prediction of Transient Fuel

Behavior with the FREY Code,"Trans.Am.Nucl.Soc., 50, 244 (1985).

15

C. V. DeVore, R. O. Montgomery, and K. L. Peddicord, "Assessment of FREY Code

Predictions of Steady State Pin Deformation," Trans.Am. Nucl.Soc., 50, 245

(1986).

D. L. Eubanks and K. L. Peddicord, "The Effect of Eccentricity on Fission Gas Release in

SP-100 Fuel Pins," Trans.Am.Nucl.Soc., 50, 249 (1985).

K. L. Peddicord, "Current Trends in Fuel Development and Future Needs in Extended

Burnup Performance Analysis," 5th International Seminar on

Mathematical/Modeling of Reactor Fuel Elements, Harwell, England, August 15-

16, 1985.

K. L. Peddicord, "Nuclear Fuels for Space Reactors," 5th International Seminar on

Mathematical/Modeling of Reactor Fuel Elements, Harwell, England, August 15-

16, 1985.

K. L. Peddicord, S. H. Lowy, B. Roberts, and J. Alred, "NASA/Universities' Advanced

Design Project Studies," Trans.Am.Nucl.Soc., 49, 33 (1985).

K. L. Peddicord and S. C. Vaughn, "Initial Stage Restructuring in Sphere-Pac Proceedings

and Mixed Carbide Nuclear Fuel," Extended Abstracts of the American Ceramic

Society, 87th Annual Meeting, p. 203, Cincinnati, OH, May 5-9, 1985.

K. L. Peddicord and D. C. Carpenter, "Restructuring Characteristics of SP-100 Oxide Fuel

Pins," Transactions of the 2nd Symposium on Space Nuclear Power Systems,

CONF-850103- Summs., p. FP-6, Albuquerque, NM, January 14-16, 1985.

Kenneth L. Peddicord, Thomas L. George, and Timothy C. Kennedy, "A Model for the

Thermal and Mechanical Behavior of Mixed Carbide Spheres for Fuel Pins,"

Nuclear Science and Engineering, Vol. 86, No. 3, 253 (1984).

T. L. George, T. C. Kennedy, and K. L. Peddicord, "An Elastic Stress-Strain Relation for

Sphere Arrays Undergoing Initial Sintering," Proceedings of the Winter Annual

Meeting of the ASME, Paper 84-WA/ APM-49, New Orleans, LA, December 9-14,

1984.

K. L. Peddicord, E. Deiss, and T. Butler, "Fuel/Cladding Thermal Conductance for Sphere-

Pac Mixed Carbide Fuel," Trans.Am.Nucl.Soc., 47, 195 (1984).

J. K. Thomas, R. O. Montgomery, and K. L. Peddicord, "The Axial Slip Behavior of a

Particle Bed in a Clad Tube," Trans.Am.Nucl.Soc., 47, 196 (1984).

K. L. Peddicord, C. V. De Vore, R. O. Montgomery, "The Steady-State Self-Initialization

Capability of the FREY Transient Fuel Code," Trans.Am.Nucl.Soc., 47, 201

(1984).

D. C. Carpenter and K. L. Peddicord, "Evaluation of Uranium Oxide Fuel for SP-100,"

Abstracts of the 9th Annual AIAA Technical Symposium, Johnson Space Center,

Houston, TX, April 26, 1984.

K. L. Peddicord, C. V. De Vore, R. O. Montgomery, A. G. Adamantiades, and M. A.

Youseffnia, "Application of the FREY Transient Fuel Code for Design Basis

Events," Trans.Am. Nucl.Soc., 46 350 (1984).

K. L. Peddicord, D. C. Carpenter, and C. T. Carpenter, "Oxygen Availability in Highly

Enriched UO2 Fuel for Space Nuclear Applications," Transactions of the 1st

Symposium on Space Nuclear Reactor Power Systems, Albuquerque, New

Mexico, January 8-13, 1984.

Timothy C. Kennedy, Thomas L. George and Kenneth L. Peddicord, "Thermalplastic

Analysis of a Sphere Pac Fuel Pin," Nuclear Engineering and Design, Vol. 75, 57

(1983).

16

Y. P. Ting and Kenneth L. Peddicord, "Heat Conduction in Eccentric Annuli,"

International Journal of Heat and Mass Transfer, Vol. 26, No. 1, 11 (1983).

Maurice J. Ades, Kenneth L. Peddicord, and Scott D. Montgomery, "Thermal Performance

Modeling of Sphere-Pac Mixed Carbide Fast Reactor Fuel," Nuclear Science and

Engineering, Vol. 84, No. 1, 47 (1983).

K. L. Peddicord, R. O. Montgomery, C. V. De Vore, and T. L. George, "Performance

Implications of Particle Sizes for Sphere-Pac Nuclear Proceedings and Fuels,"

Trans.Am. Nucl.Soc., 45, 303 (1983).

T. L. George, K. L. Peddicord, and T. C. Kennedy, "Predicting Thermal Mechanical

Behavior of Mixed-Carbide Sphere-Pac Fuel Pins," Trans.Am.Nucl.Soc., 45, 306

(1983).

R. Jenks, K. L. Peddicord, and T. C. Kennedy, "Measurement of the Internal Friction

Angle for UO2 Sphere-Pac Fuel," Trans.Am.Nucl.Soc., 44, 255 (1983).

Maurice J. Ades and Kenneth L. Peddicord, "A Model for the Conductivity of Sphere-Pac

Fuel During Restructuring," Nuclear Science and Engineering, Vol. 81, No. 4, 540

(1982).

Maurice J. Ades and Kenneth L. Peddicord, "A Model for the Effective Conductivity of

Unrestructured Sphere-Pac Fuel," Nuclear Science and Engineering, Vol. 81, No.

4, 563 (1982).

T. L. George, T. C. Kennedy, and K. L. Peddicord, "Elastic Stress-Strain Relation for

Restructuring Sphere-Pac Fuel," Trans.Am.Nucl.Soc., 43 255 (1982).

Y. P. Ting and K. L. Peddicord, "Analytical Study of Heat Conduction in Fuel Pins with an

Eccentrically Placed Pellet," Trans.Am.Nucl.Soc., 41, 316 (1982).

Mitchell E. Cunningham and Kenneth L. Peddicord, "Heat Conduction in Spheres Packed

in an Infinite Regular Cubical Array," International Journal of Heat and Mass

Transfer, Vol 24, No. 7, 1081 (1981).

R. K. Henke, K. L. Peddicord and N. K. Pedersen, "Stochastic Simulation of the Loading

of Sphere-Pac Fuel Pins," Trans.Am.Nucl.Soc., 39, 423 (1981).

A. M. Vincent, K. L. Peddicord, and J. A. Van Gulik, "Fuel-Clad Mechanical Interaction in

Simulated Sphere-Pac Fuel," Trans.Am.Nucl.Soc., 39, 423 (1981).

R. W. Stratton, M. Nicolet, J. Reindl, and K. L. Peddicord, "Sphere-Pac Carbide Fuel Pin

Thermal Calculations Compared with Post Irradiation Observations,"

Trans.Am.Nucl. Soc., 36, 294 (1981).

M. Podowski and K. L. Peddicord, "Calculation of Fission Gas Behavior Using a Diffusion

Rate Model," Trans.Am.Nucl.Soc., 36, 293 (1981).

K. L. Peddicord, "NEED's Programs to Attract the Non-traditional Students to the Nuclear

Industry," Trans.Am.Nucl.Soc., 36, 78 (1981).

J. M. Oylear and K. L. Peddicord, "Statistical Sampling of Response Surfaces for DNBR

Calculations," Proceedings of the International Seminar on Reactor Safety Heat

Transfer, September 2-5, 1980, Dubrovnik, Yugoslavia, sponsored by the

International Centre for Heat and Mass Transfer, Belgrade, Yugoslavia.

S. D. Montgomery, K. L. Peddicord, and C. W. Bennett, "Axial Shear of Simulated

Sphere-Pac Fuel," Trans.Am.Nucl.Soc., 35, 205 (1980).

J. M. Oylear and K. L. Peddicord, "Statistical Sampling of Response Surfaces for Safety

Evaluation," Trans.Am.Nucl.Soc., 34, 476 (1980).

T. E. Guidotti, L. H. Nielsen and K. L. Peddicord, "Transient Fuel Pin Temperature

Calculations Based on Describing Functions,"Trans.Am. Nucl.Soc., 34, 292 (1980).

17

C. W. Bennett, S. D. Montgomery and K. L. Peddicord, "Transient Fuel Pin Temperature

Calculations Based on Describing Functions," Trans.Am.Nucl. Soc., 34, 203

(1980).

M. J. Ades and K. L. Peddicord, "SPECKLE-I, A Computer Modeling Code for Sphere-

Pac Carbide Fuels," Trans.Am.Nucl.Soc., 32, 260 (1979).

M. J. Ades and K. L. Peddicord, "Temperature Distribution During Re-structuring of

Sphere-Pac Carbide Fuels," Trans.Am.Nucl.Soc., 32, 278 (1979).

M. J. Ades and K. L. Peddicord, "Modeling Fuel Swelling and Gas Release in Sphere-Pac

Carbide Fuels," Trans.Am.Nucl.Soc., 32, 278 (1979).

K. L. Peddicord, M. J. Ades, R. W. Stratton, and V. Ionescu, "SPECKLE-I, A Computer

Code for Sphere Pac Carbide Fuel Performance," Trans.Am.Nucl.Soc., 31, 170

(1979).

R. J. Guenther and K. L. Peddicord, "Initial Stage Restructuring in Sphere Pac Mixed

Carbide Fuels," Proceedings of the International Conference on Fast Breeder

Reactor Fuel Performance, Monterey, California, March 5-8, 1979, ISBN: 0-

89448-105-3.

Gary W. McNair and Kenneth L. Peddicord, "An Improved Finite Difference Method to

Evaluate Heat Transfer in Fuel Pins with Eccentrically Placed Pellets," Nuclear

Technology, Vol. 40, 306 (1978).

Robert N. Falotico and Kenneth L. Peddicord, "Material Release for Various Fuels

Following an HCDA in CRBR," Airborne Radioactivity, American Nuclear

Society, LaGrange Park, IL, ISBN 0-89448-400-1 (1978).

M. J. Ades, R. J. Guenther and K. L. Peddicord, "Thermal Conductivity During Initial

Stage Restructuring in Sphere Pac Fuel," Trans.Am.Nucl.Soc., 30, 531 (1978).

R. N. Falotico and K. L. Peddicord, "The Effect of Internals Vent Valves on Reflood

Following a Hypothetical PWR LOCA," Transactions of the ENS/ANS Topical

Meeting on Nuclear Power Reactor Safety, Brussels, Belgium, October 16-19,

1978.

R. J. Guenther and K. L. Peddicord, "Hot Pressing in Initial Stage Restructuring of Sphere

Pac Mixed Carbide Ceramic Fuel," Abstracts of the 1978 Fall Meeting, Nuclear

Division of the American Ceramic Society, San Diego, California, October 25-28,

1978.

M. J. Ades and K. L. Peddicord, "Prediction of the Thermal Conductivity of Sphere Pac

Fuel," Trans.Am.Nucl.Soc., 28, 552 (1978).

Barry D. Ganapol, P. McKenty, and Kenneth L. Peddicord, "The Generation of Time-

Dependent Neutron Transport Solutions in Infinite Media," Nuclear Science and

Engineering, Vol. 64, No. 1, Part II, 317 (1977).

Barry D. Ganapol, R. J. Henninger, and Kenneth L. Peddicord, "Time-Lethargy

Equivalence Relations in Neutron Transport Theory," Atomkernenergie, Bd. 29,

LFG. 4, p. 247 (1977).

M. E. Cunningham, K. L. Peddicord and A. Tripathi, "Porosity Correction to Thermal

Conductivity Based on Analytical Temperatures in Pins with Eccentric Fuel

Pellets," Trans. Am.Nucl.Soc., 27, 743 (1977).

G. W. McNair and K. L. Peddicord, "Effective Calculations of Temperatures in Pins with

Eccentric Fuel Pellets," Trans.Am.Nucl.Soc., 27, 743 (1977).

R. N. Falotico and K. L. Peddicord, "Material Release for Various Fuels Following an

HCDA in CRBR," Trans.Am.Nucl.Soc., 27, 622 (1977).

18

G. W. McNair, K. L. Peddicord, B. D. Ganapol, and R. J. Henninger, "An Evaluation of

Finite Difference Methods for Calculating Heat Transfer in Fuel Pins with

Eccentrically Placed Pellets," Proceedings of the National Topical Meeting on

Thermal Reactor Safety, American Nuclear Society, Sun Valley, Idaho, CONF-

770708, July 30 - August 4, 1977.

B. D. Ganapol, P. McKenty and K. L. Peddicord, "The Generation of Time-Dependent

Neutron Transport Solutions in Infinite Media," Proceedings of the National

Topical Meeting on Mathematics and Computation, American Nuclear Society,

Tucson, Arizona, March 27-30, 1977.

K. L. Peddicord, "The Nuclear Technology Workshop, A N.E.E.D. Project at Oregon State

University," Trans.Am.Nucl.Soc., 26, 608 (1977).

K. L. Peddicord, "An Analytical Porosity Correction of Conductivity Based on Spherical

Pores Geometry," Trans.Am.Nucl.Soc., 24, 376 (1976).

K. L. Peddicord, K. J. Cox, J. M. Henderson and K. A. Lucas, "The Effect of Porosity

Correction Models on Maximum Fuel Temperatures," Trans.Am.Nucl.Soc., 23,

440 (1976).

K. L. Peddicord , B. D. Ganapol and R. J. Henninger, "A Consistent Algorithm for the

Study of Eccentric Fuel Pellets," Trans.Am.Nucl.Soc., 22, 572 (1975).

K. L. Peddicord, "Calculated Transient Response of an LMFBR Subchannel in Turbulent

Flow," Trans.Am.Nucl.Soc., 21, 417 (1975).

B. D. Ganapol, K. L. Peddicord and R. J. Henninger, "Time-Lethargy Equivalence

Theorem in Neutron Transport Theory," Trans.Am.Nucl.Soc., 19, 412, (1974).

B. D. Ganapol, P. Benoist, K. L. Peddicord and R. J. Henninger, "An Analytical Slowing

Down Benchmark Solution," Trans.Am.Nucl.Soc., 17, 334 (1973).

Reports

P. G. Medvedev and K. L. Peddicord, “Comparative Calculations of the Thermo-

Mechanical Behavior of WWER-1000 LEU and WGMOX Fuel Pins Using

COMETHE-4D and FRAPCON-3 Steady State Fuel Performance Codes”,

Department of Nuclear Engineering, Texas A&M University, Report to Oak Ridge

National Laboratory, October, 1999.

J. Alvis, P. Bellanger, G. I. Gellene, P. G. Medvedev, and K. L. Peddicord, “Modeling of

the Performance of Weapons MOX Fuel in Light Water Reactors”, Amarillo

National Resource Center for Plutonium, ANRCP-1999-19, May, 1999.

J. K. Thomas, K. L. Peddicord, S. L. Hayes, D. J. Senor, D. E. Brozak, S. G. Smith, and J.

M. Alvis, "Final Project Report" for the project "Modeling of Advanced Fuels for

the DOE Multimegawatt Space Reactor Program" (U.S. Department of Energy

contract #DE-AC02-86NE37960.A000, 10/1/86 through 12/31/88), Department of

Nuclear Engineering, Texas A&M University, College Station, TX (1989).

J. M. Alvis, J. K. Thomas and K. L. Peddicord, "Thermal Conductivity of Cermet Fuels,"

ANFL-12-O, Advanced Nuclear Fuels Laboratory, Department of Nuclear

Engineering, Texas A&M University, College Station, TX (1989).

J. K. Thomas, D. E. Brozak, K. L. Peddicord, and S. G. Smith, "NIPer: The Nitride Fuels

Irradiation Performance Data Base, Version 1.2", ANFL-11-R, Advanced Nuclear

Fuels Laboratory, Department of Nuclear Engineering, Texas A&M University,

College Station, TX (1989).

19

S. L. Hayes, D. J. Senor, J. K. Thomas, and K. L. Peddicord, "PiLSNeR: A Properties

Library for Space Nuclear Reactors, Version 1.0," ANFL-10-R, Advanced Nuclear

Fuels Laboratory, Department of Nuclear Engineering, Texas A&M University,


K. L. Peddicord, M. A. Youseffnia, R. K. Henke, R. O. Montgomery, C. V. De Vore, and

A. G. Adamantiades, "Assessment of the FREY Transient Behavior Code, Final

Report," EPRI RP-1627-1, Electric Power Research Institute, Department of


R. O. Montgomery, K. L. Peddicord, J. K. Thomas, et al., "Final Project Report" for the

project "The Impact of Advanced Power Systems on the Evolutionary Space

Station" (NASA Lewis Research Center contract #NAG 3-820, 9/1/87 through

2/29/88), Department of Nuclear Engineering, Texas A&M University, College

Station, TX (1988).

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "A Steady State Creep Rate Correlation

for Uranium Mononitride," ANFL-9-R, Advanced Nuclear Fuels Laboratory,

Department of Nuclear Engineering, Texas A&M University, College Station, TX

(1988).

D. J. Senor, J. K. Thomas, and K. L. Peddicord, "Tensile Behavior of the Niobium- 1%

Zirconium Alloy," ANFL-8-O, Advanced Nuclear Fuels Laboratory, Department of


S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Development of a Creep Rate Porosity

Correction Factor," ANFL-7-R, Advanced Nuclear Fuels Laboratory, Department

of Nuclear Engineering, Texas A&M University, College Station, TX (1988).

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "Diffusion Coefficient of Nitrogen in

Uranium Mononitride," ANFL-5-O, Advanced Nuclear Fuels Laboratory,


(1988).

D. J. Senor, J. K. Thomas, and K. L. Peddicord, "Thermophysical Property Correlations for

the Niobium-1% Zirconium Alloy," ANFL-4-O, Advanced Nuclear Fuels

Laboratory, Department of Nuclear Engineering, Texas A&M University, College

Station, TX (1988).

J. K. Thomas, D. E. Brozak, and K. L. Peddicord, "Final Project Report" for the projects

"Empirical Modeling of Uranium Nitride Fuel" and "Evaluation of Multimegawatt

Fuel Designs" (Los Alamos National Laboratory contracts #9-X6D-1879G-1 and

#9-X6D-1878G-1, 7/7/86 through 6/30/87), Department of Nuclear Engineering,

Texas A&M University, College Station, TX (1987).

J. K. Thomas, K. L. Peddicord, D. E. Brozak, and S. L. Hayes, "Progress Report" for the

project "Modeling of Advanced Fuels for the DOE Multimegawatt Space Reactor

Program" (U.S. Department of Energy contract #DE-AC02-86NE37960.A000,

10/1/86 through 12/31/88), Department of Nuclear Engineering, Texas A&M

University, College Station, TX (1987).

S. L. Hayes, J. K. Thomas, and K. L. Peddicord, "A Young's Modulus Correlation for

Uranium Mononitride," ANFL-2-R, Advanced Nuclear Fuels Laboratory,


(1987).

F. R. Best, et al., “Comments of Preliminary Survey of 21st Century Civil Mission

Applications of Space Nuclear Power (JPL D-3547) by J. Mankins, J. Olivieri and

20

A. Hepenstal," Department of Nuclear Engineering, Texas A&M University,


J. K. Thomas, et al., "Final Project Report" for the project "Transient Behavior Modeling of

Advanced Fast Reactor Fuels" (Westinghouse Hanford Company contract #Y63-

S44-52393, 8/1/86 through 12/1/86), Department of Nuclear Engineering, Texas

A&M University, College Station, TX (1986).

J. K. Thomas and K. L. Peddicord, "Final Project Report" for the project "AXL, A Real

Time On Line Clad Stress State Predictor for Sphere Pac Pins at BOL" (Swiss

Federal Institute for Reactor Research contract, 8/1/85 through 12/31/85),


(1985).

K. L. Peddicord, "The Effect of Critical Flow and Critical Heat Flux Models on Super

SARA Thermal Hydraulic Analysis," Commission of the European Communities,

Joint Research Centre, Ispra Establishment, Ispra, Italy, Technical Note No.

I.06.19.83.18 (1983).

K. L. Peddicord, "Implementation of the REFLUX Code for Super SARA Analysis,"

Commission of the European Communities, Joint Research Centre, Ispra

Establishment-Italy, Technical Note No. I.06.19.82.109 (1982).

K. L. Peddicord and I. M. Shepherd, "Material Property and Thermodynamic Subroutines

for Super SARA Analysis," Commission of the European Communities, Joint

Research Centre, Ispra Establishment-Italy, Technical Note No. I.06.19.82.110

(1982).

K. L. Peddicord, "Estimation of Maximum Fuel Temperatures for Super SARA LB-LOCA

with Control Rod Failure," Commission of the European Communities, Joint

Research Centre, Ispra Establishment-Italy, Technical No. I.06.19.82.111 (1982).

T. L. George and K. L. Peddicord, "SPECKLE-III, A Code to Predict the Thermal and

Mechanical Behavior of Sphere Pac Mixed Carbide Fuel Pins," OSU-EIR-64,

Department of Nuclear Engineering, Oregon State University, Corvallis, OR

(1982).

R. Nijsing, et al., "Super SARA Test Analysis: Outline of Approach and Reports and

Others Present Status," Super SARA Test Programme, Commission of the

European Communities, Joint Research Centre, Ispra Establishment, Ispra, Italy,

November 1981.

T. E. Guidotti, K. L. Peddicord, and L. H. Nielsen, and R. K. Henke, "Transient Fuel Pin

Temperature Calculations Using Describing Functions," EPRI NP-2278, Electric

Power Research Institute, Palo Alto, CA (1981).

T. L. George, T. C. Kennedy, and K. L. Peddicord, "A Preliminary Model for the

Mechanical Behavior of Sphere Pac Fuel Pins," OSU-EIR-56, Department of

Nuclear Engineering, Oregon State University, Corvallis, OR (1981).

T. L. George and K. L. Peddicord, "The Stress Distribution in a Regular Packed Bed of

Spheres Under Compression," OSU-EIR-55, Department of Nuclear Engineering,

Oregon State University, Corvallis, OR (1981).

T. L. George and K. L. Peddicord, "SPECKLE-II: A Code for Modeling the Thermal

Behavior of Mixed Carbide Sphere Pac Fuel," OSU-EIR-54, Department of


21

T. L. George and K. L. Peddicord, "Modeling Initial Stage Sintering," OSU-EIR-53,


(1981).

C. A. Robinson and K. L. Peddicord, "BURNUP User's Guide," OSU-EIR-52, Department

of Nuclear Engineering, Oregon State University, Corvallis, OR (1981).

K. L. Peddicord, "Summary of Research Activities for the Present: Modeling and

Characterization of Sphere Pac Mixed Carbide Fuel, " OSU-EIR-51, Department of


K. L. Peddicord, S. D. Montgomery and R. W. Stratton, "Calculations of the Thermal

Behavior of Sphere-Pac Carbide Fuel Pins Under Start-up Conditions in the U.S.

Fast Flux Test Facility Using the Code SPECKLE-I," Swiss Federal Institute for

Reactor Research, Würenlingen, Switzerland, EIR-Bericht NR. 396, Department of

Nuclear Engineering, Oregon State University, OSU-NE-8002 (1980).

E. P. Coomes, J. M. Oylear and K. L. Peddicord, "A Summary of the Thermal Hydraulic

Analysis Codes COBRA-III C/MIT, COBRA-IV-I and THINC," Department of

Nuclear Engineering, Oregon State University, OSU-NE-8001 (1980).

C. W. Bennett, A. M. Vincent, and K. L. Peddicord, "Description of the JVG-I Apparatus

for Investigating the Fuel Clad Mechanical Interaction of Sphere Pac Fuel," OSU-

EIR-50, Department of Nuclear Engineering, Oregon State University, Corvallis,

OR (1980).

K. L. Peddicord and T. L. George, "Code Modifications to SPECKLE-I," OSU-EIR-49,


(1980).

K. L. Peddicord, S. D. Montgomery, and C. W. Bennett, "Visit Report to EIR, August 20

to September 8, 1980," OSU-EIR-48, Department of Nuclear Engineering, Oregon

State University, Corvallis, OR (1980).

K. L. Peddicord, “Finite Element Methods for Fuel Pin Mechanical Analysis, Application

to SPECKLE-I," OSU-EIR-47, Department of Nuclear Engineering, Oregon State

University, Corvallis, OR (1980).

K. L. Peddicord, "Summary of Research Activities for the Project: Evaluation Models for

the Prediction of the Performance of Sphere Pac Mixed Carbide Fuel--Part II,"

OSU-EIR-46, Department of Nuclear Engineering, Oregon State University,

Corvallis, OR (1980).

K. L. Peddicord and C. A. Robinson, "Visit Report, Eidgenössisches Institut für

Reaktorforschung and the Transuranium Institute," OSU-EIR-45, Department of


M. Ades and K. L. Peddicord, "A Description of the SPECKLE-I Code," OSU-EIR-44,


(1979).

C. A. Robinson and K. L. Peddicord, "RPBURN: A Program for the Numerical Solution of

the Burnup Equations," OSU-EIR-42, Department of Nuclear Engineering, Oregon


K. L. Peddicord and C. A. Robinson, "Visit Report, Battelle Northwest Laboratory, Exxon

Nuclear Company, and the Hanford Engineering Development Laboratory," OSU-


OR (1979).

22

K. L. Peddicord, "Summary of Research Activities, January 1-December 31, 1978," OSU-


OR (1979).

K. L. Peddicord and M. Ades, "Visit Report to EIR, the EURATOM Transuranium

Institute Karlsruhe, and AERE Harwell," OSU-EIR-39, Department of Nuclear

Engineering, Oregon State University, Corvallis, OR (1978).

R. J. Guenther, F. Jafarey, and K. L. Peddicord, "Computer Programs Used in the Study of

Sintering Mechanisms for Carbide Microspheres," OSU-EIR-37, Department of


M. Ades and K. L. Peddicord, "Evaluation of the Thermal Effective Conductivity of Sphere

Pac Fuel During Initial Stage Restructuring," OSU-EIR-36, Department of Nuclear


K. L. Peddicord, "Summary of Research Activities, Evaluation Models for the Prediction of

the Performance of Sphere Pac Fuel Pins, January 1-June 30, 1978," OSU-EIR-35,


(1978).

M. Ades and K. L. Peddicord, "SPECKLE, A Computer Code for the Prediction of the

Behavior of Sphere Pac Mixed Carbide Fuel in an LMFBR, Part I. Analysis,"

OSU-EIR-34, Department of Nuclear Engineering, Oregon State University,

Corvallis, OR (1978).

M. Ades and K. L. Peddicord, "Modeling of the Thermal and Mechanical Behavior of

LMFBR Fuel Elements, Part II. Carbide Fuels," OSU-EIR-33, Department of


M. Ades and K. L. Peddicord, "Modeling of the Thermal and Mechanical Behavior of

LMFBR Fuel Elements, Part I. Oxide Fuels," OSU-EIR-31, Department of Nuclear


K. L. Peddicord, "Summary of Research Activities, Heat Transfer in Sphere Pac Fuel Pins,

September 1, 1977 to December 31, 1977," OSU-EIR-29, Department of Nuclear


R. J. Guenther and K. L. Peddicord, "Sintering Processes in Mixed Carbides," OSU-EIR-

28, Department of Nuclear Engineering, Oregon State University, Corvallis, OR

(1978).

M. Ades and K. L. Peddicord, "TPSGAS, TPSBIN: A Numerical Model for the Evaluation

of the Effective Conductivity of a Sphere Pac Unit Cell," OSU-EIR-26, Department


K. L. Peddicord, "Visit Report to EIR, August 24 to September 15, 1977," OSU-EIR-25,


(1977).

K. L. Peddicord, "Summary of Research, Heat Transfer in Sphere Pac Reactor Fuel Pins,

September 16, 1975 to August 31, 1977," OSU-EIR-24, Department of Nuclear


K. L. Peddicord and R. J. Guenther, "Restructuring Mechanisms in (U0.8,Pu0.2)C Pellets

and (U0.85,Pu0.15)C Sphere Pac Fuel," OSU-EIR-23, Department of Nuclear


M. Ades and K. L. Peddicord, "A Model for the Calculation of the Effective Thermal

Conductivity of an Irradiated Sphere Pac Unit Cell," OSU-EIR-22, Department of


23

M. Ades and K. L. Peddicord, "TEMPC, TEMPC1: Two Numerical Models for the

Evaluation of the Effective Conductivity of a Sphere Pac Unit Cell--Computation

Results, and Comparison with Existing Models," OSU-EIR-21, Department of


M. Ades and K. L. Peddicord, "Gas Gap Models for Heat Transfer Calculations in a

Sphere Pac Unit Cell," OSU-EIR-20, Department of Nuclear Engineering, Oregon


M. E. Cunningham and K. L. Peddicord, "Porosity Correction to Thermal Conductivity

Based on Analytical Temperature Solutions--ANS Summary and Paper," OSU-


OR (1977).

K. L. Peddicord and D. F. Elger, "Summary of UNCLE1," OSU-EIR-18, Department of


J. C. Reis and K. L. Peddicord, "NUMCFR, A Program to Calculate One-Dimensional

Temperature Profiles in Sphere Pac Fuel Pins," OSU-EIR-17, Department of


M. Ades and K. L. Peddicord, "TEMPS, and TEMP1-Two Computer Programs for

Solving Two- Dimensional Steady State Heat Conduction Problems is a Sphere Pac

Unit Cell," OSU-EIR-16, Department of Nuclear Engineering, Oregon State


K. L. Peddicord and J. C. Reis, "A Note on the Thermal Conductivity of Fission Gases

with Helium," OSU-EIR-13, Department of Nuclear Engineering, Oregon State


M. Ades and K. L. Peddicord, "Heat Flow in a Sphere Pac Unit Cell," OSU-EIR-12,


(1977).

K. L. Peddicord, "Annual Report on the Project Heat Transfer in Sphere Pac Fuel, January

1, 1976 to December 31, 1976," OSU-EIR-11, Department of Nuclear


M. E. Cunningham and K. L. Peddicord, "Report on TEMPRO1: Description, Results, and

Comparison with TEMP1," OSU-EIR-10, Department of Nuclear Engineering,

Oregon State University, Corvallis, OR (1977).

K. L. Peddicord, "An Analytical Porosity Correction of Conductivity Based on Spherical

Pore Geometry--ANS Summary and Results," OSU-EIR-9, Department of Nuclear


K. L. Peddicord, "Semi-Annual Report, January, 1976-June 30, 1976," OSU-EIR-7,


(1976).

J. M. Henderson and K. L. Peddicord, "CFT3R, A Three Region Model and Code for

Temperature Calculations in Sintered Sphere Pac Fuel Pins with a High Porosity

Central Region," OSU- EIR-6, Department of Nuclear Engineering, Oregon State


K. L. Peddicord and M. E. Cunningham, "Project Heat Transfer in Sphere Pac Fuel:

Effective Thermal Conductivity of the Unit Cell, Part I: Analytical Development of

Temperature Solutions in a Sphere," OSU-EIR-5, Department of Nuclear


24

K. L. Peddicord, K. J. Cox, J. M. Henderson, and K. A. Lucas, "A Note on Expressions for

Thermal Conductivity for Uranium-Plutonium Carbide," OSU-EIR-3, Department


K. L. Peddicord, K. A. Lucas, J. M. Henderson, and K. J. Cox, "The Effect of Porosity

Corrections Models on Centerline Temperatures in a Partially Sintered Sphere Pac

Fuel Pin, Calculations with Program CFT," OSU-EIR-2, Department of Nuclear


K. L. Peddicord, K. A. Lucas, J. M. Henderson, and K. J. Cox, "A Review of Corrections

to Thermal Conductivity of Ceramic Reactor Fuels due to Porosity," OSU-EIR-1,


(1976).

L. Smith, K. L. Peddicord, H. Leute, P. Buetzer, and B. Burgisser, "The Post Irradiated

Examination of the FILOS 04 Rig Containing Two Instrumented (U,Pu) C Sphere-

Pac Fuel Pins Würenlingen," EIR Report 193, Swiss Federal Institute for Reactor

Research, Würenlingen, Switzerland (1975).

K. L. Peddicord and H. Leute, "Foil Measurements and Neutronics Calibrations for the

FILOS 05 Irradiation," EIR-TM-IN-605, PPR-345, Swiss Federal Institute for

Reactor Research, Würenlingen, Switzerland (1975).

K. L. Peddicord and L. Smith, "Temperature Calculations in (U,Pu)C Sphere-Pac Fuel,"

EIR-TM-IN-602, PPR-341, Swiss Federal Institute for Reactor Research,

Würenlingen, Switzerland (1975).

K. L. Peddicord, "Neutron Transport Calculations with the WIMS Code for the FILOS and

DIDO Elements," EIR-TM-IN-590, PPR-314, Swiss Federal Institute for Reactor


K. L. Peddicord, "Data Input for ORTHIS," EIR-TM-IN-590, PPR-314, Swiss Federal

Institute for Reactor Research, Würenlingen, Switzerland (1975).

K. L. Peddicord, "A Heat Transfer Model to Calculate Temperature Profiles in (U,Pu)C

Sphere-Pac Fuel Pins," EIR-TM-IN-590, PPR-314, Swiss Federal Institute for


L. Smith, K. L. Peddicord, P. Buetzer, P. Rickenbacker, and B. Burgisser, "The Post

Irradiation Examination of Four (U,Pu)C Sphere-Pac Fuel Pins Irradiated in the

DIDO Reactor at Harwell," EIR Report 265, Swiss Federal Institute for Reactor


K. L. Peddicord and H. Leute, "Foil Irradiations in SAPHIR for FILOS 05," EIR-TM-IN-

581, PPR-281, Swiss Federal Institute for Reactor Research, Würenlingen,

Switzerland (1974).

M. Baggenstos and K. L. Peddicord, "Reaktivitätsrechnungen eins SR-III Brennelement

mit Vier Energiegruppen," EIR-TM-IN-581, PPR-284, Swiss Federal Institute for


F. Stierli, K. L. Peddicord, and R. Stratton, "(U,Pu)C Bestrahlungsversuch FILOS 04

bestimmung der Brennstoffleistung," EIR-TM-IN 552, PPR-232, Swiss Federal

Institute for Reactor Research, Würenlingen, Switzerland (1973).

K. L. Peddicord, "The Status of Reactor Physics Calculations for FILOS," EIR-TM-IN-

430, PPR-216, Swiss Federal Institute for Reactor Research, Würenlingen,

Switzerland (1972).

25

K. L. Peddicord, "Two-Group Cross Section with Burnup for the SR-III Loading," EIR-

TM-IN- 523, PPR-198, Swiss Federal Institute for Reactor Research, Würenlingen,

Switzerland (1972).

K. L. Peddicord, "Transport Calculations for the FILOS 04 Irradiation Element," EIR-TM-

IN-521, PPR-195, Swiss Federal Institute for Reactor Research, Würenlingen,

Switzerland (1972).

K. L. Peddicord, "The Effect of Gamma Heating on FILOS Linear Power and Temperature

Calculations," EIR-TM-IN-503, PPR-160, Swiss Federal Institute for Reactor


K. L. Peddicord, "The Influence of Various Hydrodynamic Models in the Calculations of

Power Level and Temperature Response for Mild Transients in Fast Assemblies,"

Ph.D. Thesis, Nuclear Engineering Program, University of Illinois, Urbana, Illinois

(1972).

H. G. Stoll, K. L. Peddicord, G. C. Cavanaugh, and A. B. Chilton, "Application of the

ILLIAC IV Computer to Monte Carlo Radiation Transport," UILV-ENG 71 5302,

Nuclear Engineering Program, University of Illinois, Urbana, Illinois (1971).

G. P. Beck, et al., "Safety Analysis Report for the Illinois Advanced TRIGA," University of

Illinois, Nuclear Engineering Program, Urbana, Illinois, (1967).

26

RESEARCH

Funded Research Projects (Texas A&M University)

“Nuclear Process Heat for the Clean and Efficient Utilization of the Fossil Resource”,

funded by the U.S. Department of Energy Nuclear Energy Research Initiative,

$225,000, August 1, 1999 to July 31, 2003.

“Remote Monitoring and Control of Proliferation Resistant Reactors” (with W. D. Reece

and R. B. Williams), funded by the U.S. Department of Energy Nuclear Energy

Research Initiative, $275,000, August 1, 1999 to July 31, 2002.

“Fuel Performance Modeling of MOX Fuel in U.S. and Russian Light Water Reactors,”

funded by Oak Ridge National Laboratory, $25,000, January 16, 1999 to January

15, 2000.

“Modeling and Characterization of the Performance of MOX Fuel in Light Water Reactors

Under High Burnup Conditions” funded by Belgonucléaire, S.A., $95,168,

September 1, 1998 to August 31, 1999.

“Literature Study of the Fission Gas Release of High Burnup UO2 Fuel,” funded by the

Anatech Corporation, $20,454, June 1, 1998 to September 30, 1998.

“Nuclear Materials Safety Management Initiative Advance Research Workshop,” (with

Leonard Lazerev, Khlopin Radium Institute), funded by the North Atlantic Treaty

Organization, $56,500, December 1, 1996 to May 31, 1997.

“Support of Workshop on Aerosol Monitoring,” (with Kerry Kinney, University of Texas at

Austin, and Andrew McFarland, Texas A&M University), funded by the U.S.

Department of Energy and the Los Alamos National Laboratory, $108,000,

December 1, 1996 to May 31, 1997.

“MOX Fuel Performance Evaluation,” funded by the Amarillo National Resource Center

for Plutonium/University of Texas at Austin, $224,868, June 1, 1996 to January 15,

1999.

“Higher Education Consortium/Amarillo National Resource Center for Plutonium,” (with

Dale E. Klein, University of Texas System, Kathleen Harris, Texas Tech

University, and Wales E. Madden, Jr., Panhandle 2000), funded by the U. S.

Department of Energy, $44,000,000, April 20, 1995 to June 30, 2000.

“Project Definition Study,” (with R. E. Ewing), funded by the Texas National Research

Laboratories Commission, $105,006, June 1, 1994 to September 30, 1994.

"Investigation of Natural and Man-Made Radiation Effects on Crews on Long Duration

Space Missions," (with W. E. Bolch, A. G. Parlos, and J. W. Poston) funded by the

NASA Lewis Research Center, Cleveland, OH, $100,000, June 1, 1992 to May 31,

1993.

"Design and Feasibility Studies for TOPAZ-II Derivative Reactor," (with A. G. Parlos)

funded by the Center for the Commercialization of Space Power, Texas

Engineering Experiment Station, $40,000, March 27, 1991 to May 31, 1993.

"Design and Feasibility Studies for TOPAZ-II Derivative Reactor," (with A. G. Parlos)

funded by the NASA Lewis Research Center, Cleveland, OH, $99,793, March 27,

1991 to May 31, 1993.

"Institute for National Drug Abatement Research," funded by the U. S. General Services

Administration, Washington, D.C., $1,000,000, October 1, 1990 to September 30,

1991.

27

"The Radiological Impact of Space Nuclear Power Applications," (with W. E. Bolch)

funded by the NASA Lewis Research Center, Cleveland, OH, $75,000, October

15, 1989 to October 14, 1990.

"The Design of a Multifunctional Shield for Space Station Operations," (with W. E. Bolch)

funded by the NASA Office of Exploration, $29,830, July 1, 1989 to January 31,

1990.

"NASA/Universities Space Research Association Advanced Design Program," (with Y. A.

Hassan) funded by the Universities Space Research Association, $27,447, June 1,

1988 to August 31, 1988.

"The EPRI/NEDHO Nuclear Engineering Faculty Workshop on Exploratory Research,"

funded by the Electric Power Research Institute, Palo Alto, CA, $5,198, September

1, 1988 to December 31, 1988.

"Assessment and Application of a Transient Fuel Behavior Code," funded by the Electric

Power Research Institute, Palo Alto, CA, $11,653, September 1, 1988 to December

31, 1988.

"A Multi-Reactor Configuration for Multi-Megawatt Spacecraft Power Supplies," funded

by NASA Headquarters, $10,000, June 1, 1988 to February 28, 1989.

"Assessment and Application of a Transient Fuel Behavior Code," funded by the Electric

Power Research Institute, Palo Alto, CA, $27,059, January 1, 1988 to August 31,

1988.

"Analysis of the Uncertainties in Irradiation Capsule Temperature Distributions," funded by

the NASA Center for the Commercialization of Space Power, Texas A&M

University, $51,194, August 1, 1988 to June 31, 1989.

"The Radiological Impact of Space Nuclear Power Applications," funded by the NASA

Lewis Research Center, Cleveland, OH, $75,000, October 15, 1988 to October 14,

1989.

"Fuel Rod Analysis with COMETHE III-L," funded by Belgionucleaire, S.A., $26,370,

January 1, 1987 to December 31, 1990.

"NASA/University Advanced Design Program," (with S. H. Lowy) funded by the

University Space Research Association, $22,484, September 1, 1987 to August 31,

1988.

"Impact of Advanced Power Systems on the Evolutionary Space Station," funded by the

NASA Lewis Research Center, $49,496, September 15, 1987 to February 29,

1988.

"Assessment & Application of a Transient Fuel Behavior Computer Code," funded by the

Electric Power Research Institute, $34,370, June 29, 1987 to December 31, 1987.

"Manned Mars Mission Project," (with S. H. Lowy) funded by the University Space

Research Associates, $22,484, September 1, 1986 to August 31, 1987.

"Evaluation of the Integral Effects of Fuel Element Thermal Analysis Methodologies,"

funded by the U.S. Nuclear Regulatory Commission, $24,639, March 1, 1987 to

February 28, 1988.

"Modeling of Advanced Fuels for the DOE Multimegawatt Space Reactor Program,"

funded by the U.S. Department of Energy, $133,000, October 1, 1987 to

September 30, 1988.

"Modeling of Advanced Fuels for the DOE Multimegawatt Space Reactor Program,"

funded by the U.S. Department of Energy, $129,000, October 1, 1986 to

September 30, 1987.

28

"University Advanced Space Design Program," (with S. H. Lowy) funded by the

University Space Research Associates, $21,060, September 1, 1985 to August 31,

1986.

"Empirical Modeling of Uranium Nitride Fuel," funded by Los Alamos National

Laboratory, $31,599, July 7, 1986 to May 30, 1987.

"Evaluation of Multimegawatt Fuel Designs," funded by Los Alamos National Laboratory,

$32,000, July 7, 1986 to May 30, 1987.

"Transient Behavior Modeling of Fast Reactor Fuels," funded by the Westinghouse

Hanford Corporation, $29,634, March 1, 1987 to August 1, 1987.

"High Burnup Fuel Rod Evaluation with the COMETHE Fuel Performance Code," funded

by Belgonucleaire, S.A., $4,500, September 1, 1986 to December 31, 1986.

"Assessment & Application of a Transient Fuel Behavior Computer Code," funded by the

Electric Power Research Institute, $89,681, April 30, 1983 to December 31, 1986.

"Fuel Performance Codes: Reliability Prediction and Forecasting," funded by the Hanford

Engineering Development Laboratory, Richland, WA, $19,221, October 1, 1985 to

September 31, 1986.

"Real Time Stress-Strain Predictor for Sphere-Pac Nuclear Fuel Pins," funded by the Swiss

Federal Institute for Reactor Research, Würenlingen, Switzerland, $9,997, June 15,

1985 to December 31, 1985.

"Methodologies to Assess Lifetime Limits for Extended Burnup Fuel," funded by the

Nuclear Regulatory Commission, Washington, D.C., $24,939, April 1, 1985 to

March 31, 1986.

"NASA/Universities Advanced Design Project, Manned Mars Space Mission," (with S.H.

Lowy) funded by the Johnson Space Center, Houston, TX, $39,050, January 15,

1985 to August 31, 1985.

"PWR Steam Generator Modeling Using the RETRAN Code," (with G. A. Schlapper and

F.R. Best) funded by Houston Lighting and Power Company, Houston, TX,

$48,064, January 1, 1985 to December 31, 1985.

"Empirical Temperature Correlations and Performance Modeling for Advanced Carbide

Fuel," funded by the Los Alamos National Laboratory, Los Alamos, NM $95,745,

October 1, 1984 to September 30, 1986.

"Assistance to Los Alamos National Laboratory on the AC-3 Advanced Carbide Fuel

Test," funded by the Los Alamos National Laboratory, $44,586, November 28,

1983 to August 31, 1984.

"Assessment and Application of the FREY Code with Emphasis on Transient

Initializations," funded by the Electric Power Research Institute, Palo Alto,

California , $70,708, June 1, 1983 to December 31, 1986.

Funded Research Projects (Oregon State University)

"Assessment and Application of Transient Fuel Behavior Computer Codes," funded by the

Electric Power Research Institute, Palo Alto, California, $24,977, January 1, 1982

to December 31, 1982.

"Transient Analysis of a Pressurized Water Reactor," funded by the Portland General

Electric Company, Portland, Oregon, $29,242, September 16, 1981 to September

15, 1982.

29

"Modeling and Characterization of Sphere-Pac Mixed Carbide Fuel," funded by the Swiss

Federal Institute for Reactor Research, Würenlingen, Switzerland, $52,569,

September 16,1981 to December 31, 1982.

"Modeling and Characterization of UO2 Sphere-Pac Fuel," funded by the Exxon Nuclear

Company, Richland, Washington, $63,650, June 16, 1981 to December 31, 1982.

"Sphere-Pac Fuel in a Safeguarded Fuel Cycle-Part II," (with B. I. Spinrad) funded jointly

by the Electric Power Research Institute, Palo Alto, California, and the Swiss


January 1, 1981 to September 30, 1981.

"Transient Thermal Hydraulic Analysis of a Pressurized Water Reactor," funded by the

Portland General Electric Company, Portland, Oregon, $26,803, September 16,

1980 to September 15, 1981.

"Characterization of UO2 Sphere-Pac Fuel," funded by the Exxon Nuclear Company,

Richland, Washington, $36,614, March 16, 1980 to September 15, 1981.

"Assessment and Application of Transient Fuel Behavior Computer Codes--Part II,"

funded by the Electric Power Research Institute, Palo Alto, California, $22,042,

January 1, 1981 to December 31, 1981.

"Modeling and Characterization of Sphere-Pac Mixed Carbide Fuel," funded by the Swiss


September 16, 1980 to September 15, 1981.

"Assessment and Application of Transient Fuel Behavior Computer Codes," funded by the



"Heat Conduction in Eccentric Annuli," funded by the National Science Foundation,

$72,811, December 15, 1979 to October 31, 1982.

"Evaluation Models for the Prediction of the Performance of Sphere-Pac Mixed Carbide

Fuel Pins- Part III," funded by the Swiss Federal Institute for Reactor Research,

Würenlingen, $33,719, January 1, 1980 to September 15, 1980.

"Transient Fuel Pin Temperatures Based on Describing Functions--Part II," funded by the



"Thermal Hydraulic Analysis of a Pressurized Water Reactor--Part II," funded by the

Portland General Electric Company, Portland, Oregon $22,823, September 16,

1979 to September 15, 1980.

"Sphere-Pac Ceramic Fuel in a Safeguarded Fuel Cycle," (with B. I. Spinrad), funded

jointly by the Electric Power Institute, Palo Alto, California and the Swiss Federal

Institute for Reactor, Würenlingen, Switzerland, $44,274, September 16, 1979 to

December 31, 1980.


Fuel Pins--Part II," funded by the Swiss Federal Institute for Reactor Research,

Würenlingen, Switzerland, $47,534, January, 1979 to December 31, 1979.

"Transient Fuel Pin Temperature Algorithms Based on Transfer Functions," funded by the

Electric Power Research Institute, Palo Alto, California, $25,000, September 16,

1978 to December 31, 1979.

"Thermal Hydraulic Analysis of a Pressurized Water Reactor Core," funded by the Portland

General Electric Company, Portland, Oregon, $16,601, June 16, 1978 to June 15,

1979.

30


Fuel Pins--Part I," funded by the Swiss Federal Institute for Reactor Research,

Würenlingen, Switzerland, $33,896, January 1, 1978 to December 31, 1978.

"Heat Transfer in Sphere-Pac Reactor Fuel Pins--Part II," funded by the Swiss Federal

Institute for Reactor Research, Würenlingen, Switzerland, $19,117, January 1,

1977 to December 31, 1977.

"Heat Transfer in Sphere-Pac Reactor Fuel Pins," funded by the Swiss Federal Institute for

Reactor Research, Würenlingen Switzerland, $19,980, January 1, 1976 to

December 31, 1976.

HUMAN RESOURCE DEVELOPMENT FOR THE NUCLEAR INDUSTRY

Funding to the Nuclear Power Institute

International Atomic Energy Agency, March 22, 2014 to April 11, 2014, HEU-TAMU

Joint Training Project, $51,000.

International Atomic Energy Agency, Group Fellowship Training, November 15, 2014 to

December 31, 2014, $36,000

International Atomic Energy Agency, Kenyan Training Program, June 1, 2014 to July 31,

2014, $82,927

International Atomic Energy Agency, Group Fellowship Training, January 15, 2014 to

February 28, 2014, $49,192

Texas Legislature (through the Texas A&M Engineering Experiment Station), September

1, 2013 to August 31, 2015, $3 million

Ministry of Higher Education of Turkey, Scientific Training and Trips for Visiting

Professors, June 1, 2013 to August 31, 2013, $9,260

International Atomic Energy Agency, Kenyan Training Program, June 1, 2013 to August

15, 2013, 82,000

International Atomic Energy Agency, Nuclear Energy Management School Sponsorships,

March 1, 2013 to March 31, 2013, $12,500

Idaho National Laboratory, International Framework for Nuclear Energy Cooperation

Workshop, June 1, 2014 to July 31, 2014, $31,712

International Atomic Energy Agency, Kenyan Training Program, June 1, 2012 to August

15, 2012, $158,318

United Kingdom, nucleargraduates Programme, January 15, 2012 to February 29, 2012,

$4,500

Texas Legislature (though the Texas Engineering Experiment Station), September 1, 2011

to August 31, 2013, $3 million

Texas Legislature (through the Texas Higher Education Coordinating Board), September

1, 2009 to August 31, 2011, $4 million

Texas Legislature (though the Texas Engineering Experiment Station), September 1, 2009

to August 31, 2011, $1 million

Texas Workforce Commission, September 1, 2009 to August 31, 2010, $1 million

Texas Workforce Commission, September 1, 2008 to August 31, 2009, $1 million

GRADUATE ADVISING

31

Graduate Theses and Dissertations Advised (Texas A&M University)

Moshin Reza, “Design Modification for the Modular Helium Reactor for Higher

Temperature Operation and Reliability Studies for Nuclear Hydrogen Production

Processes ”, Doctor of Philosophy, Department of Nuclear Engineering (2007).

Pavel Medvedev, “Development of Dual Phase Magnesia-Zirconia Ceramics for Light

Water Reactor Inert Matrix Fuel”, Doctor of Philosophy, Department of Nuclear

Engineering (2004).

Galina Tsvetkova, “Analysis of the Modular Helium Reactor for a Hydrogen Production

Plant”, Doctor of Philosophy, Department of Nuclear Engineering (2003).

Anton Moisseytsev, “Passive Load Follow Analysis of the STAR-LM and the STAR-H2

Systems”, Doctor of Philosophy, Department of Nuclear Engineering (2003).

Phillipe Belanger, “Performance of Weapons MOX Fuel in Light Water Reactors,” Master

of Science Degree, Department of Nuclear Engineering, (1999).

Christopher C. Allison, “Simulation Of MOX Fuel Thermal Gradients To Study Gallium

Interactions,” Master of Science Degree, Department of Nuclear Engineering

(1999).

Vanessa L. Gonzalez (co-chair with David Hill), “U.S. Weapons-Usable Plutonium

Disposition Policy: Implementation of the Mixed Oxide Option,” Master of Arts

Degree, Department of Poltical Science, (1998).

David J. Senor (co-chair with L. R. Cornwell), "High Volume Fraction Metal Matrix

Composites Cast Under Bi-Dimensional Compression", Doctor of Philosophy,

Department of Nuclear Engineering (1992).

Steven L. Hayes, "Numerical Analysis of Radiative Heat Transfer in Porous Uranium

Dioxide Fuel", Doctor of Philosophy, Department of Nuclear Engineering (1992).

Marc-Emmanuel G. Portal (co-chair with B. Nassersharif), "Decision Making Under

Uncertainty in Nuclear Engineering Design," Doctor of Philosophy, Department of

Nuclear Engineering (1992).

James Kelly Thomas, "The Activated Heat Source Concept for Space Power Applications",

Doctor of Philosophy, Department of Nuclear Engineering (1992).

Daniel L. DeForest, "Transient Fission Gas Behavior in Uranium Nitride Fuel Under

Proposed Space Applications," Doctor of Philosophy, Department of Nuclear

Engineering (1991).

Steven L. Hayes, "Material Property Correlations for Uranium Mononitride," Master of

Science Degree, Department of Nuclear Engineering (1989).

David J. Senor, "Material Property Correlations for the Niobium-1% Zirconium Alloy,"

Master of Science Degree, Department of Nuclear Engineering (1989).

Jeffrey W. Simmons, "An Evaluation of thermal Modeling Techniques Utilized for Nuclear

Fuel Rods," Master of Science Degree, Department of Nuclear Engineering (1989).

Jeffrey George, "A Multi-Reactor Configuration for Multi-Megawatt Spacecraft Power

Supplies," Master of Science Degree, Department of Nuclear Engineering (1989).

Eric W. Bechler, "Evaluation of Fuel Rod Characterization for Transient Fuel Modeling,"


William F. Lyon, III, "Development of a Computational Model for Nuclear Electric Orbital

Transfer Vehicles, " Master of Science Degree, Department of Nuclear Engineering

(1989).

John Alvis, "Cermet Fuel Thermal Conductivity," Master of Science Degree, Department

of Nuclear Engineering (1988).

32

Daniel E. Brozak, "Empirical Modeling Of Uranium Nitride Fuels," Master of Science

Degree, Department of Nuclear Engineering (1987).

Marc-Emanuel G. Portal, "Creep Measuring Device For Low Melting Point Metals,"


Robert O. Montgomery, "Secondary Side Model Development for the Westinghouse

Model E Steam Generator," Master of Science Degree, Department of Nuclear

Engineering (1987).

Curtis V. De Vore, "Methodologies To Assess Potential Lifetime Limits For Extended

Burnup Nuclear Fuel," Master of Science Degree, Department of Nuclear

Engineering (1986).

James Kelly Thomas, "Axial Clad Strain Behavior of Sphere-pac Fuel Pins," Master of

Science Degree, Department of Nuclear Engineering (1986).

David C. Carpenter, "A One-dimensional, Time-dependent Integral Analysis of SP-100

Space Reactor Fuel Pins," Master of Science Degree, Department of Nuclear

Engineering (1986).

Dion J. Sunderland, "Loss Of Particles Through A Clad Breach In A Simulated Sphere-

Pac Fuel Pin," Master of Science Degree, Department of Nuclear Engineering

(1985).

Graduate Theses and Dissertations Advised (Oregon State University)

R. J. Jenks, "Direct Shear Testing of UO2 Sphere-Pac Nuclear Fuel," Master of Science


T. L. George (co-chair with T. C. Kennedy) "A Model for the Mechanical Behavior of

Irradiated Mixed Carbide Sphere-Pac Fuel Pins," Doctor of Philosophy,

Department of Mechanical Engineering (1982).

Bahram Nassersharif, "Describing Function Theory as Applied to Nuclear Engineering

Problems," Doctor of Philosophy, Department of Nuclear Engineering (1982).

P. T. Reardon, "Porosity Corrections to Conductivity for Nuclear Fuels," Master of Science


Peter B. Chadly, (co-chair with K. Hornyik) "Thermal Hydraulic Analysis of a U-Tube

Steam Generator in a PWR," Master of Science Degree, Department of Nuclear

Engineering (1983).

Gary W. McNair, "Natural Convection in Horizontal Eccentric Annuli," Doctor of

Philosophy, Department of Nuclear Engineering (1982).

James S. Willison, "Thermal Conductivity Modeling of Unrestructured Sphere-Pac Nuclear

Fuel," Master of Science Degree, Department of Nuclear Engineering, OSU-NE-

8110 (1982).

Andrew M. Vincent, "Fuel Clad Mechanical Interaction of Simulated Graduated Sphere-

Pac Fuel," Master of Science Degree, Department of Nuclear Engineering, OSU-

NE-8203 (1981).

Cheryl A. Robinson, "Heat Source and Burnup Algorithms for a Sphere-Pac Mixed

Carbide Fuel Pin," Master of Science Degree, Department of Nuclear Engineering,

OSU-NE-8105 (1981).

Robert K. Henke, "The Effect of Packing Density on the Thermal Conductivity of Sphere-

Pac Nuclear Fuels," Master of Science Degree, Department of Nuclear

Engineering, OSU-NE-8108 (1981).

33

Scott D. Montgomery, "Thermal and Mechanical Behavior of Sphere-Pac Fuel," Master of

Science Degree, Department of Nuclear Engineering, OSU-NE-8106 (1981).

Y. P. Ting, "Heat Condition in Eccentric Annuli," Doctor of Philosophy, Department of

Nuclear Engineering, OSU-NE-8104 (1981).

L. H. Nielsen, "An Assessment of Describing Function Methods Applied to Reactor Fuel

Performance Analysis," Master of Science Degree, Department of Nuclear


E. P. Coomes, "Thermal Hydraulic Analysis of a Pressurized Water Reactor During

Transient Conditions," Master of Science Degree, Department of Nuclear


Timothy E. Guidotti, (co-advisor with W. Holley) "Transient Temperature Algorithms

Using Transfer Functions," Master of Science Degree, Department of Mechanical


Maurice Ades, "Modeling of the Thermal Behavior of Irradiated Sphere-Pac Mixed

Carbide Fuel," Doctor of Philosophy, Department of Nuclear Engineering, OSU-

NE-7902 (1979).

Joan Oylear, "Thermal Hydraulic Analysis of a Pressurized Water Reactor Core," Master

of Science Degree, Department of Nuclear Engineering, OSU-NE-7906 (1979).

Richard J. Guenther, "The Applicability of Sintering Mechanisms in the Initial Stage

Restructuring and Preferential Pore Migrated of Irradiated (U85%, Pu15%)C Sphere-

Pac Fuel," Master of Science Degree, Department of Nuclear Engineering, OSU-

NE-7809 (1978).

Gary W. McNair, "An Evaluation of Finite Difference Methods for Calculating Heat

Transfer in Fuel Pins with Eccentrically Placed Pellets," Master of Science Degree,

Department of Nuclear Engineering, OSU-NE-7704 (1977).

Mitchell E. Cunningham, "Temperature Profiles of Spheres Packed in Regular Arrays,"

Master of Science Degree, Department of Nuclear Engineering, OSU-NE-7804

(1977).

kenneth lee peddicord - tamu college of engineeringkenneth lee peddicord director nuclear power...

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