resume of timothy d. burchell - oak ridge national … of tim burchell... · 1981-1983...

Resume of Timothy D. Burchell

July 2016


I. PERSONAL Present Position: Distinguished R&D Staff Member

Battelle Distinguished Inventor Nuclear Materials Science & Technology Group Materials Science & Technology Division Oak Ridge National Laboratory, PO Box2008, Oak Ridge, TN 37831-6132,USA.

II. EDUCATION Degrees University Dates B.Sc (Hons). University of Bath, UK. 1978-1981 [Materials Science] Ph.D University of Bath, UK 1983-1986 [Studies of Fracture in Nuclear Graphite] III. ACADEMIC HONORS AND AWARDS Pergamon Prize for best paper published in CARBON journal, 1986-1987

Duke of Edinburgh's Gold Award 1983 (for demonstrated civic responsibility and achievement)

Plenary Lecturer: CARBON '96 Conference, Newcastle Upon Tyne, UK. July 1996.

ORNL/Lockheed Martin Technical Achievement Award, 1998 ORNL/Lockheed Martin Engineer of the Year, 1998 R&D-100 Award, 1999 (Self-Cleaning Carbon Air Filter) R&D-100 Award, 2000 (ORNL High Thermal Conductivity Graphite Foam) SAE International “Excellence in Oral Presentation”, June 2000 Federal Laboratory Consortium for Technology Transfer 2000 Award for Excellence in Technology Transfer


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Federal Laboratory Consortium for Technology Transfer 2001 Award for Excellence in Technology Transfer Federal Laboratory Consortium for Technology Transfer 2003 Award for Excellence in Technology Transfer American Carbon Society 2002/03 Graffin Lecturer Battelle Distinguished Inventor Hsun Lee Lecture Award, Chinese Academy of Science’s Institute of Metals Research, in recognition of past accomplishments in the field of Materials Science (2006) Fellow of the American Carbon Society (elected July 2007) HTR2010 Best Presentation at Conference Plenary Lecturer, CARBON ’10 Conference, Clemson University, Clemson, SC, USA ASME Certificate of Acclamation, Aug 2011 ASTM International D02 Eagle Award, June 2015

IV. PROFESSIONAL EXPERIENCE 1974-1978 Technician Apprentice, Plessey Aerospace, Titchfield, England. 1981-1983 Metallurgist, Plessey Aerospace, Titchfield, England.

1986-1988 Research Officer, CEGB Berkeley Nuclear Laboratories, Berkeley, England.

1989-1991 Research Staff Member, Oak Ridge National Laboratory, Oak Ridge, USA.

1991-2013 Leader, Carbon Materials Technology Group, ORNL, USA. 2013-2016 Distinguished R&D Staff Member, Fusion Material & Nuclear

Structures Group, ORNL, USA 2016-Present Nuclear Graphite Team Leader and Distinguished R&D Staff

Member, Nuclear Material Science & Technology Group, ORNL, USA

V. PROFESSIONAL SERVICE

A. Membership in Professional Societies: The Institute of Materials, Minerals and Mining; The American Carbon Society; American Society for the Testing and Materials; American Society of Mechanical Engineers

B. Meeting Committee Memberships: Organizing Committee, Fifth International

Conference on Fusion Reactor Materials (ICFRM-5), Program Committee ICFRM-5, Program Chairperson, Industrial Applications Session, 20th Biennial Conference on Carbon. Advisory Committee, Workshop on Coal Derived Graphite, Coke and Pitch,


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West Virginia University. Chairman of 1994 American Carbon Society Workshop entitled "Carbon Materials for Advanced Technologies". Program Chairperson, Industrial Applications Session, 22nd Biennial Conference on Carbon. Member, International Advisory/Program Committee, IAEA Specialists Meeting on Graphite Moderator Lifecycle Technologies. Technical Program Chair, 24th Biennial Conference on Carbon, Charleston, SC. June, 1998. Chairman, INGSM-1 (2000), Technical Program Committee Member-INGSM-VI (2005). Chairman, INGSM-7 (2006). Chairman CARBON 2007. Member International Advisory Committee, CARBON 2009.

Guest Editor: Special Edition Journal of Nuclear Materials Vol 381 (2008).

C. Society Service:

I. Member, Council of the Institute of Materials (1988).

II. Member of Advisory Board of the American Carbon Society (1993-99) and (2007-2010).

III. Awards Committee Chair, American Carbon Society (1996-2002). IV. Secretary/Treasurer, American Carbon Society (1999-2004) V. Technical Program Chair, 24th Biennial Conf on Carbon, CARBON ’99, July

1999, Charleston SC. VI. Member of ASTM DO2-F Committee on Manufactured Carbons and Graphites

(1988-2002) and (2014-present). VII. Sub-Committee Chair ASTM D02-F2 on Nuclear Graphite (2000-2003).

VIII. Chair ASTM Committee D02-F on Manufactured Carbon and Graphite (2002 – 2014).

IX. Member, ASTM D02 Committee on Petroleum Products (2002-present) X. Chair, ASME Project Team on Graphite Core Support Structures (2004-2006)

XI. Chair, ASME Sub Group on Graphite Core Support Structures (2006-2013) XII. Member, ASME Sub Group on Graphite Core Support Structures (2006-

Present) XIII. Chair, Seventh International Nuclear Graphite Specialist’s Meeting (INGSM-

VII), September 10-13, 2006 XIV. Chair, CARBON 2007 Conference, Seattle WA, July 15-20, 2007 XV. Member ASME SC III on Nuclear Power (2007 – present)

XVI. Co-Chair, Fourteenth International Nuclear Graphite Specialist’s Meeting (INGSM-XIV), September 15-18, 2013

D. Associate Editor, CARBON (1995-2003)

E. Editor, CARBON (2003-2009)

F. Member, Honorary Editorial Board, CARBON (2010-Present)

G. Member, Scientific Advisory Board of National Center for Fibers and Films, Clemson

University, Clemson SC., USA. (2002-2006) H. American Carbon Society 2002/03 Graffin Lecturer


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I. Member for the USA on the IAEA Nuclear Graphite Irradiated Properties Database Steering Committee (1999-present)

J. International Coordinator for the Graphite R&D Tasks (Gen IV Very High

Temperature Reactor Project Management Board for Materials) and Chairman of Gen IV International Forum Graphite Working Group (2005-2008).

K. Member Associate Editorial Board of the Journal of Nuclear Materials (2006-2014)

VI. RESEARCH INTERESTS Graphite, carbon-carbon composites, carbon fiber properties. Synthesis of novel carbon products. The effects of neutron irradiation on the mechanical and physical properties of graphite. Graphite irradiation creep behavior. Modeling of graphite properties. Fracture of graphite. Acoustic emission. Application of NDE to graphites and carbon-carbon composites. Development of carbon-carbon composites for nuclear applications. Adsorbent carbons, including carbon fibers and fibrous monoliths. High temperature nuclear fuels. Nuclear Graphite Codes & Standards VII PATENTS

US Patent Number 5,332,601, Jul 26, 1994 US Patent Number 5,744,075, Apr 28, 1998 US Patent Number 5,827,355, Oct 27, 1998 US Patent Number 5,871,838, Feb 26, 1999 US Patent Number 5,912,424, Jun 15, 1999 US Patent Number 5,925,168, Jul 20, 1999 US Patent Number 5,972,077, Oct 26, 1999 US Patent Number 6,030,698, Feb 29, 2000 US Patent Number 6,037,032, Mar 14, 2000 US Patent Number 6,037,073, Mar 14, 2000 US Patent Number 6,090,477, Jul 18, 2000 US Patent Number 6,171,720, Jan 9, 2001 US Patent Number 6,258,300, Jul 10, 2001 US Patent Number 6,375,716, Apr 23, 2002 US Patent Number 6,399,149, Jun 4, 2002 US Patent Number 6,475,411, Nov 5, 2002 US Patent Number 6,673,328, Jan 6, 2004 US Patent Number 6,780,505, Aug 24, 2004 US Patent Number 7,014,151, Mar 21, 2006 US Patent Number 7,070,755, Jul 4, 2006 US Patent Number 7,157,019, Jan 2, 2007

US Patent Number 7,166,237, Jan 2, 2007


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VIII. OPEN LITERATURE PUBLICATIONS T. D. Burchell, R. G. Cooke, B. McEnaney and I. M. Pickup. Acoustic Emission from Graphite - the Effect of Texture. In Ext. Abs. & Prog. Carbone 84, Bordeaux, France. July 2-6,1984, p.110. T. D. Burchell, R. G. Cooke, B. McEnaney and I. M. Pickup. The Influence of Radiolytic and Thermal Oxidation on the Mechanical Properties of Nuclear Graphites. In Ext. Abs. & Prog. 17th Biennial Conf. on Carbon, Lexington, Kentucky, USA. June 16-21, 1985, p.336. T. D. Burchell, B. McEnaney, A. P. G. Rose and M. O. Tucker. The influence of Grain Size Distribution on a Fracture Criterion for Graphites. ibid p.346. T. D. Burchell, R. G. Cooke, B. McEnaney and I. M. Pickup. Acoustic Emission from Polygranular Graphites. CARBON Vol. 23, No. 6, pp. 739-747, 1985. T. D. Burchell, B. McEnaney, M. O. Tucker and A. P. G. Rose. A Microstructural Study of Dynamic Crack Propagation in Nuclear Graphites. In Ext. Abs. & Prog. Carbon 86, Baden -Baden, FRG. June 6 - July 4, 1986. p. 265. M. O. Tucker, A. P. G. Rose and T. D. Burchell. The Fracture of Polygranular Graphites. CARBON Vol. 24, No. 5, pp. 582-602, 1986. PERGAMON PRIZE WINNER. T. D. Burchell, I. M. Pickup, B. McEnaney and R. G. Cooke. The Relationship Between Microstructure and the Reduction of Elastic Modulus in Thermally and Radiolytically Corroded Nuclear Graphites. CARBON Vol.24, No.5, pp. 545-549, 1986. T. D. Burchell, A. P. G. Rose and B. McEnaney. Acoustic Emission from Irradiated Nuclear Graphite. Journal of Nuclear Materials Vol. 140, No.1, pp.11-18, Aug. 1986. T. D. Burchell and A. J. Wickham. The Dimensional Change in Pile Grade A Graphite Irradiated in CEGB Magnox Power Reactors. In Ext. Abs. & Prog. 18th Biennial Conf. on Carbon, Worcester, Mass., USA. July 16-20, 1987. p. 245. T.D. Burchell and M. O. Tucker. A New Fracture Criterion for Nuclear Graphites. ibid p.486. T. D. Burchell and A. P. G. Rose. The Influence of Irradiation on the Acoustic Emission of a Nuclear Graphite. ibid p. 488. T. D. Burchell, M. O. Tucker and B. McEnaney. Qualitative and Quantitative Studies of Fracture in Nuclear Graphites. In Proc. Conf. on Materials for Reactor Core Applications. British Nuclear Energy Society. Oct. 17-29, 1987. Bristol, UK. p. 95. T. D. Burchell. Ultrasonic Studies of a Nuclear Graphite. In Ext. Abs & Proc. Carbon 88, Newcastle upon Tyne, UK. p. 552. T. D. Burchell, T. Oku and M. Eto. A Comparison of Fracture Toughness Measurement Techniques as Applied to Nuclear Graphite. In Ext. Abs. & Prog. Carbone 90, Paris, France. July 16-20, 1990. p. 278.


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E. L Fuller, Jr., B. R. Chilcoat, T. D. Burchell, T. Oku and M. Eto. Chemical and Morphological Effects in the Reaction of Graphite with Water Vapor. ibid p. 534. M. Eto, S. Ishiyama, Y. Nishiyama, T. Oku and T. D. Burchell. Fracture Toughness of a Fine Grained Nuclear Graphite by Means of Various Methods. In Proc. International Symposium on Carbon - New Processing and New Applications, Tsukuba, Japan, Nov 4-8, 1990. T. D. Burchell and W. P. Eatherly. The Effects of Radiation Damage on the Properties of GraphNOL N3M. J. Nucl. Mater. Vol. 179-181, pp. 205-208, 1991. D. J. Varacalle, Jr., H. Herman, G. A. Bancke, T. D. Burchell and G. R. Romanoski. Vacuum Plasma Sprayed Silicon Coatings. Surface and Coatings Technology, Vol. 49, pp. 24-30, 1991. T. D. Burchell, E. L. Fuller, Jr., G. R. Romanoski, Jr. and J. P. Strizak. Graphite for the Nuclear Industry. In Proc. Workshop on Coal Derived Graphite, Coke and Pitch. West Virginia University, May 2-3, 1991. T. D. Burchell, W. P. Eatherly, G. W. Hollenberg, O. D. Slagle and R. D. Watson. The Effects of Neutron Irradiation on the Structure of Carbon-Carbon Composites. In Ext. Abs. & Prog. 20th Biennial Conf. on Carbon, UCSB, Santa Barbara, Ca, USA, June 23-28, 1991. p.598. G. R. Romanoski, Jr. and T. D. Burchell. Specimen Size Effects on Fracture Toughness of Nuclear Graphites. ibid p.584. J. P. Strizak and T. D. Burchell. The Effect of Stress Volume on the Tensile Properties of Graphite. ibid p.586. R. B. Dinwiddie, T. D. Burchell and C. F. Baker. Investigation into the Effect of Heat Treatment on the Thermal Conductivity of 3-D Carbon/Carbon Composites. ibid p.642. J. W. Sapp, Jr., D. A. Bowers, R. B. Dinwiddie and T. D. Burchell. Development of High Thermal Conductivity Carbon-Carbon Composites. ibid p. 644. T. D. Burchell. A Microstructurally Based Fracture Model for Nuclear Graphite. Proceedings of the IAEA Specialists Meeting on the Present Status of Graphite Development for Gas Cooled Reactors, JAERI Tokai, Japan. September 9-12, 1991. IAEA-TECDOC-690, Feb 1993. G. R. Romanoski and T. D. Burchell. The Effect of Specimen Geometry and Size on the Fracture Toughness of Nuclear Graphites. ibid. T. D. Burchell, W. P. Eatherly, JM. Robbins and J. P. Strizak. The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials. J. Nucl. Mater., Vol. 191-194, pp. 295-299, 1992. T. D. Burchell, W. P. Eatherly and G. E. Nelson. Radiation Damage in Carbon-Carbon Composites. In Proc. CARBON 92, Essen, Germany, July 22-26, 1992. p. 985.


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T. D. Burchell and J. P. Strizak. Modeling the Tensile Strength of H-451 Nuclear Graphite. In Ext Abs & Proc, 21st Biennial Conf. on Carbon. SUNY at Buffalo, June 13-18, 1993. p. 687. Y. Q. Fei, B. McEnaney, F. J. Derbyshire and T. D. Burchell. Microstructural Characterization of 3D Cabon-Carbon Composites, 1. A systematic Observation of Structure by by SEM. ibid, p. 64. Y. Q. Fei, B. McEnaney, F. J. Derbyshire and T. D. Burchell. Microstructural Characterization of 3D Carbon-Carbon Composites, 2. A Quantitative Study by SEM Digital Imagr Analysis. ibid, p. 66. T. D. Burchell. The Temperature Dependence of Thermal Conductivity in NP-MHTGR Fuel Compacts. ibid, p. 695. T. D. Burchell and W. P. Eatherly. Neutron Irradiation Induced Changes in the Dimensions and Thermal Conductivity of Carbon-Carbon Composites. ibid. p.697. B. T. Kelly and T. D. Burchell. Irradiation Creep in Nuclear Reactor Graphite. ibid, p. 709. T. D. Burchell. Fusion Energy - A Challenge to the Carbon Material Scientist. Energeia, Vol. 4, No. 6, 1993. B. T. Kelly and T. D. Burchell. The Analysis of Irradiation Creep Experiments on Nuclear Reactor Graphite. CARBON Vol. 32, No.1, pp 119-125, 1994. T. D. Burchell. Irradiation Induced Structure and Property Changes in Tokamak Plasma- Facing, Carbon-Carbon Composites. In Proc 39th SAMPE Symposium, Vol. 39, pp. 2423-2436, 1994. T. D. Burchell, C. E. Weaver, F. Derbyshire, Y. Fei, and M. Jagtoyen. Carbon Fiber Composite Molecular Sieves: Synthesis and Characterization. In Proceedings of Carbon '94 International Conference, Granada, Spain, July 4-8, 1994. p. 650. T. D. Burchell and J. P. Strizak. The Performance of a Fracture Model for Graphites. In Proceedings of Carbon '94 International Conference, Granada, Spain, July 4-8, 1994. p. 128. T. D. Burchell, C. E. Weaver, F. Derbyshire, Y. Fei, and M. Jagtoyen. Carbon Fiber Composite Molecular Sieves: Activation, Pore Structure and Adsorptive Behavior. In Proceedings of Carbon '94 International Conference, Granada, Spain, July 4-8, 1994. p. 654. B. T. Kelly and T. D. Burchell. Structure-Related Property Changes in Polycrystalline Graphite under Neutron Irradiation. CARBON Vol. 32, No.3, pp 499-505, 1994. T. D. Burchell. Carbon Fiber Composite Molecular Sieves. In Proceedings of Eight Annual Conference on Fossil Energy Materials, Oak Ridge, Tennessee, U.S.A., May 1994. ORNL/FMP-94/1, CONF-9405143, pp. 63-70. Pub. Oak Ridge National Lab, U.S.A., August 1994.


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F. Derbyshire, Y. Q. Fei, M. Jagtoyen, G. Kimber, M. Matheny and T. D. Burchell. Carbon Fiber Composite Molecular Sieves for Gas Separation. In Advances in Science and Technology, 4. New Horizens for Materials (Proceedings of Eight CIMTEC World Ceramics Congress, Florence, Italy, June 28 - July 2, 1994.), P. Vincenzini, Ed. p.411. Pub. Techna, Faenza, Italy, 1995. M. Jagtoyen, F. Derbyshire, N. Custer and T. D. Burchell. Carbon Fiber Composite Molecular Sieves for Gas Separation. In Proceedings of the 1994 MRS Spring Meeting, San Francisco, California, April 4-8, 1994. Vol. 344. Materials Research Society, Pittsburgh, 1994. T. D. Burchell, J. W. Klett and C. E Weaver. A Novel Carbon Fiber Based Porous Carbon Monolith. In Proceedings of Ninth Annual Conference on Fossil Energy Materials, Oak Ridge, Tennessee, U.S.A., May 1995. Pub. Oak Ridge National Lab, U.S.A.. CONF-9505204, ORNL/FMP/-95/1, pp. 447-456 (1995) T. D. Burchell. Modeling the Strength of Neutron Irradiated Graphite. In Ext Abs & Proc, 22nd Biennial Conf. on Carbon. UCSD, July 16-21, 1995. p. 768. L. L. Snead and T. D. Burchell. Reduction in Thermal Conductivity due to Neutron Irradiation. ibid, p.774. J. W. Klett and T. D. Burchell. Carbon Fiber Carbon Composites for Catalyst Supports. ibid, p. 124. L. L. Snead and T. D. Burchell. Thermal Conductivity Degradation of Graphite due to Neutron Irradiation at Low Temperatures. J. Nucl. Mater. 244 (1995) 222-229. T. D. Burchell and R. R. Judkins. Passive CO2 Removal using a Carbon Fiber Composite Molecular Sieve, Energy Conservation and Management Vol. 37, Nos. 6-8, pp. 947-954 (1996) T. D. Burchell. A Microstructurally Based Fracture Model for Polygranular Graphites, CARBON Vol 34 No.3, pp. 297-316 (1996) T. D. Burchell. Radiation Damage in Carbon-Carbon Composites: Structure and Property Effects, Physica Scripta Vol. T64, pp. 17-25 (1996) T. D. Burchell. Carbon Materials for Advanced Energy Applications, In Proc CARBON '96. pp. 185-188, Pub. The British Carbon Group (1996). T. D. Burchell. A Monolithic Carbon-Fiber Based Composite Adsorbent, In Proc. CARBON '96. pp. 749-750, Pub. The British Carbon Group (1996). S. Ishiyama, T. D. Burchell, J. P. Strizak and M. Eto. The Effect of High Fluence Neutron Irradiation on the Properties of a Fine-Grained Isotropic Nuclear Graphite, Journal of Nuclear Materials Vol. 230, pp. 1-7 (1996).


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T. D. Burchell and R. R. Judkins. A Novel Carbon Fiber Based Material and Separation Technology, Energy Conservation and Management Vol. 38 Suppl., pp. S99-S104, 1997. T. D. Burchell, R. R. Judkins and M. R. Rogers. A Novel Parametric Swing Process for the Separation of Hydrogen from Coke Oven Waste Gas. In Proc. US/JAPAN Joint Technical Workshop on Coal Liquefaction and Materials for Coal Liquefaction, Penn. State University, State College Pa. USDOE (1996). T. D. Burchell, R. R. Judkins, M. R. Rogers and A. M. Williams. A Novel Approach to the Removal of CO2. In Proc. 10th An. Conf. on Fossil Energy Materials. ORNL/FMP-96/1, CONF -9605167, Oak Ridge National Laboratory, U.S.A. pp. 135 - 148 (1996). G. R. Romanoski and T. D. Burchell, Method for Reinforcing Threads in Multilayer Composite Tubes and Cylindrical Structures. Ceramic Engineering and Science Proceedings Vol. 17, No. 4, pp. 90-97, (1996), Pub. American Ceramics Society. T. D. Burchell, R. R. Judkins, and M. R. Rogers. A Carbon Fiber Based Monolithic Adsorbent for Gas Separation. In Proc.23rd Biennial Conf. On Carbon, July 18-23, 1996, p. 158. T. D. Burchell, R. R. Judkins, M. R. Rogers and A. M. Williams, A Novel Process for the Separation of Carbon Dioxide and Hydrogen Sulfide for Gas Mixtures, CARBON, Vol. 35, No. 9, pp. 1279-1294 (1997). T. D. Burchell. Radiation Effects in Graphite and Carbon-Based Materials, MRS Bulletin. Vol. XXII, No. 2, Feb. 1997, pp. 29-35 . Burchell, T.D. and Rogers, M.R., Carbon fiber composite molecular sieves, In Proc. Eleventh Annual Conf. On Fossil Energy Materials, ORNL/FMP-97/1, CONF-9705115, Oak Ridge National Lab, U.S.A., 1997, pp. 109 116. T. D. Burchell, R. R Judkins, M. R. Rogers and W. S. Shaw, The Structure and Properties of Carbon Fiber Based Adsorbent Monoliths, In Proc. International Symposium of Carbon, p. 506, Tokyo, Japan, (1998) K. Nakanishi, T. Arai and T. Burchell, Assessment of Brittle Fracture Theory bases on Mesoscopic Fracture Mechanics of Multiple Grain/Pore Systems in Graphite and SIC, In Proc. International Symposium of Carbon, p. 332, Tokyo, Japan, (1998) T. Burchell, R. Judkins and M. Rogers, The Adsorption of Water Vapor on Carbon Fiber Composite Molecular Sieves, In Proc 12th Annual Conf on Fossil Energy Materials, Pub. Oak Ridge National Lab. (1998) J. P Strizak, T. D. Burchell and M. R. Rogers, Carbon Fiber Composite Molecular Sieve and Electrical Swing Adsorption Technology for the Separation and Capture of Carbon Dioxide, In Proc 13th Annual Conf on Fossil Energy Materials, Pub. Oak Ridge National Lab. (1999) T. M. Besmann, J. W. Klett, and T. D. Burchell, “Carbon Composite for a PEM Fuel Cell,” in Materials for Electrochemical Energy Storage, eds. D. S. Ginley, D. H. Doughty, T. Takamura, Z. Zhang, and B. Scrosati, Vol. 496, Materials Research Society, Warrendale, PA 1999.


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James Klett, Claudia Walls and Tim Burchell, High-Thermal-Conductivity, Mesophase-Pitch-Derived Carbon Foams: Effect of Precursor on Structure and Properties, In Proc. 24th Biennial Conf. On Carbon, July 11-16, 1999, p. 132 S. Hellebust, R. A. Daley, R. H. Bradley and T. D. Burchell, Carbon Fiber Monoliths: A Study of Surface Chemistry and Water Adsorption, In Proc. 24th Biennial Conf. On Carbon, July 11-16, 1999, p. 320 Tim Burchell and Rod Judkins, A Novel Adsorbent Carbon Fiber Composite Molecular Sieve Gas Separation Media, In Proc. 16th Annual International Pittsburgh Coal Conference, Pub University of Pittsburgh (1999) James Klett, Lynn Klett, Tim Burchell, Claudia Walls, "Graphitic Foam Thermal Management Materials for Electronic Packaging, Proceedings of the Society of Automotive Engineering Future Car Congress, Crystal City, Washington, DC, April 2-6, 2000.

James Klett, Rommie Hardy, Ernie Romine, Claudia Walls , Tim Burchell, High-Thermal-Conductivity, Mesophase-Pitch-Derived Carbon Foams: Effect of Precursor on Structure and Properties, CARBON Vol. 38 (7), pp. 953-973 (2000).

T. D. Burchell and M. R. Rogers, Natural Gas Storage Monoliths Based on Activated Carbon Fibers, In Proc. EUROCARBON 2000, p. 133, July 2000 T. Oku, A. Kurumada, B. McEnaney, T. D. Burchell, M. Ishihara, K. Hayashi, S. Baba. Ion Irradiation Effect on Different Carbon Fibers, In Proc. EUROCARBON 2000, p. 947, July 2000 T. D. Burchell, Gas Separation Using a Carbon Fiber Composite Molecular Sieve, In Proc 14th Annual Conf on Fossil Energy Materials, Pub. Oak Ridge National Lab. (2000) Tim Burchell and Mike Rogers, Low Pressure Storage of Natural Gas for Vehicular Applications, SAE Paper 2000-01-2205, Pub. Society of Automotive Engineers, Inc. (2000) Tim Burchell, Rod Judkins, Alex Gabbard, Omats Omatete and Mike Rogers, Development of Novel Activated Carbon Composites, In Proc 15th Annual Conf on Fossil Energy Materials, Pub. Oak Ridge National Lab. (2001) E. L. Fuller, T. D. Burchell and M.R. Rogers, Energetics and Mechanism of Physical Sorption on Carbonaceous Solids: Grafoil Flexible Carbon, In Proc. 25th Biennial Conf. On Carbon, July 2001 Tim Burchell, Alex Gabbard, Jane Howe and Mike Rogers, Natural Gas Storage Monoliths Based on Carbon Fibers, In Proc. 25th Biennial Conf. On Carbon, July 2001 James Klett , Nidia Gallego, Tim Burchell, Jeff Bailey, Irradiation Studies of Graphite Foams and Effects on Properties for Use in a Solid State Self-regulating Nuclear Heat Source for Small Modular Power Units, In Proc. 25th Biennial Conf. On Carbon, July 2001 A. Kurumada, T. Oku, B. McEnaney, T.D. Burchell, M. Ishihara, K. Hayashi, S. Baba and J. Aihara, Ion Irradiation Effects on Mechanical Properties and Microstructures of Different Carbon Fibers, In Proc. 25th Biennial Conf. On Carbon, July 2001


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T. D. Burchell, Nuclear Graphite and Radiation Effects, In. Encyclopedia of Materials: Science and Technology, pp. 6309-6319, Pub Elsevier Science Ltd. (2001) T. D. Burchell, Radiation Effects in Carbon-Carbon Composites, In. Encyclopedia of Materials: Science and Technology, pp. 7972-7975, Pub Elsevier Science Ltd. (2001) T. D. Burchell. Neutron Irradiation Damage in Graphite and it Effects on Properties. Paper No. H095. In Proceedings of the International Carbon Conference CARBON 2002, Beijing, China, September 2002. T. D. Burchell. Carbon Fiber Composite Adsorbent Media for Low Pressure Natural Gas Storage. Energia Vol. 13, No. 3 (2002) Timothy R. Armstrong, Lynn B. Klett, Dane F. Wilson, Timothy Burchell and Roddie R. Judkins. A Regenerable CO2 Scrubber for Alkaline Fuel Cells, In Proceedings US Fuel Cell Seminar, Nov. 18-21, 2002, Palm Springs, CA. Tim Burchell, Jane Howe, Alex Gabbard, and Mike Rogers. Adsorbent Carbon Fiber Composites for the Storage of Natural Gas, In. Proc. 48th International SAMPE Symposium, pp. 1855-1867, Pub. Society for the Advancement of Materials and Process Engineering (2003) Nidia C Gallego, Timothy D. Burchell, James W. Klett. Neutron Irradiation Damage in Graphite Foam and its Effects on Properties, In Proc CARBON ’03, July 2003, Oviedo, Spain. Pub. Spanish Carbon Group (2003) L.L. Snead, T.D. Burchell, A.L. Qualls. Strength of Neutron Irradiated High-Quality 3D Carbon Fiber Composite. J. Nucl. Mater. 321 (2003) 165-169. T. D. Burchell, M Srinivasen and D. Naus. Codes and Standards Development For Graphite-Moderated Nuclear Reactors. In. Basic Studies in the Field of high temperature Engineering, Third International Exchange Meeting, Iberaki-ken, Japan, 11-12 September, 2003. pp 33-39, Pub. Nuclear Energy Agency, OECD (2004). J. W. Klett, A. D. McMillan, N. C. Gallego, T. D. Burchell, C. A. Walls. Effects of heat treatment conditions on the thermal properties of mesophase pitch-derived graphitic foams. CARBON 42 (2004) 1849-1852 N. C. Gallego and T. D. Burchell, Carbon Materials for Hydrogen Storage, ANS/ENS International Winter Meeting, New Orleans, LA, USA, Nov. 16-20, 2003. N. C. Gallego, T. D. Burchell and A. M. Clark, Carbon Materials for Hydrogen Storage, In Proc CARBON 2004, An International Conference on Carbon, Providence Rhode Island, July 11-16, 2004. Pub. American Carbon Society T. D. Burchell, O. Omatete, N. C. Gallego, and F. S. Baker, “Use of Carbon Fiber Composite Molecular Sieves for Air Separation,” Adsorption Science & Technology, 23(3), pp. 175-194 (2005).


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A. Striolo, K.E. Gubbins, M.S. Gruszkiewicz, D.R. Cole, J.M. Simonson, A.A. Chialvo, P.T. Cummings, T.D. Burchell, K.L. More, Effect of Temperature on the Adsorption of Water in Porous Carbons, Langmuir, 21, pp. 9457-9467 (2005). C.W. Forsberg, T.D. Burchell, D.F. Williams, D.E. Holcomb, R F Holdaway and A.L.Qualls, Carbon-Carbon-Composite Salt-Cooled Electric Space Reactors, Proc ANS Space Nuclear Conference 2005. San Diego, Paper 1148, (2005) N. C. Gallego, T. D. Burchell, James W. Klett, Irradiation effects on graphite foam, CARBON, 44, pp. 618-628 (2006). C. I. Contescu, N. C. Gallego, J. M. Pickel, D. A. Blom, and T. D. Burchell, “Carbon fiber composite monoliths for catalyst supports” Prepr. Pap.-Am. Chem. Soc., Div. Fuel Chem. 2006, 51 (1), 120-121. Timothy D. Burchell and Lance L. Snead, The Effect of Neutron Irradiation Damage on the Properties of Grade NBG-10 Graphite, In. Proc CARBON 2006 (July 2006) Cristian I. Contescu, Frederick S. Baker, and Timothy D. Burchell, Development of an ASTM Graphite Oxidation Test Method, In. Proc CARBON 2006 (July 2006) Cristian I. Contescu, Frederick S. Baker, Nidia C. Gallego, Timothy D. Burchell, and Roddie R. Judkins, Regenarable Carbon Fiber Composite Molecular Sieves for Scrubbing CO2 from Air , In. Proc CARBON 2006 (July 2006) Cristian I. Contescu, Frederick S. Baker, and Timothy D. Burchell, Surface Chemistry and Water Dispersability of Carbon Black Materials, In. Proc CARBON 2006 (July 2006) Cristian I. Contescu, Nidia C. Gallego, Joseph M. Pickel, Douglas A. Blom, and Timothy D. Burchell, Carbon Fiber Composite Monoliths as Catalyst Supports, In. Proc CARBON 2006 (July 2006) Frederick S. Baker, Cristian I. Contescu, Nidia C. Gallego, and Timothy D. Burchell, Carbon Fiber Composite Molecular Sieves for Air Separation, In. Proc CARBON 2006 (July 2006) T. D. Burchell & J. P. Strizak, Graphite for Next Generation Reactors, In Proc. ANS 2006 Annual Meeting, Reno NV, June 2006. Tim Burchell, Terry Yahr, and Rick Battiste, Modeling the Multiaxial Strength of Nuclear Grade Graphite, In Proc HTR-2006, Johannesburg, South Africa. Timothy D. Burchell and Lance L. Snead, The Effect of Neutron Irradiation Damage on the Properties of Grade NBG-10 Graphite, Journal of Nuclear Materials 371 (2007) 18-27. Tim Burchell, Terry Yahr, and Rick Battiste, Modeling the Multiaxial Strength of Nuclear Grade Graphite, CARBON 45 (2007) 2570-2583 Cristian I. Contescu, Frederick S. Baker, Rodney D. Hunt, Jack L. Collins, and Timothy D. Burchell. Selection of water-dispersible carbon black for fabrication of uranium oxicarbide microspheres, Journal of Nuclear Materials, 375 (2008) 38-51.


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Timothy D. Burchell, Irradiation Induced Creep Behavior of H-451 Graphite, Journal of Nuclear Materials, 381 (2008) 46-54. L.L. Snead, T.D. Burchell, and Y Katoh, Swelling of Nuclear Graphite and High Quality Carbon Fiber Composite Under Very High Irradiation Temperature, Journal of Nuclear Materials, 381 (2008) 55-61. C.I. Contescu, S. Azad, D. Miller, M.J. Lance, F. S. Baker, and T. D. Burchell, Practical Aspects for Characterizing Air Oxidation of Graphite, Journal of Nuclear Materials, 381 (2008) 15-24. P.J. Pappano, T.D. Burchell, J.D. Hunn, M.P. Trammell. A Novel Approach to Fabricating Fuel Compacts for the Next Generation Nuclear Plant (NGNP), Journal of Nuclear Materials, 381 (2008) 25-38. J.L. McDuffee, T.D. Burchell, D.W. Heatherly, K.R. Thoms, Experimental Plan and Design of Two Experiments for Graphite Irradiation at Temperatures Up To 1500 ºC in the Target Region of the High Flux Isotope Reactor, Journal of Nuclear Materials, 381 (2008) 114-118. J.L. McDuffee, T.D. Burchell, D.W. Heatherly, K.R. Thoms, Preliminary Design of a Graphite Irradiation Tensile Creep Experiment in the Target Region of the High Flux Isotope Reactor, Journal of Nuclear Materials, 381 (2008) 119-123. L.L. Snead, Y. Katoh, W. Windes, R. Shinavski, T.D. Burchell, Ceramic Composites for Near Term Reactor Applications, Proc. 4th International Topical Meeting on High Temperature Reactor Technology (HTR-2008), Sept 28-Oct 1, 2008. Paper No. HTR2008-58050 S. H. Chi C. I. Contescu, and T. D. Burchell, Density Change of an Oxidized Nuclear Graphite by Acoustic Microscopy and Image Processing, EGT&P Vol. 131 (2009) 052904-1-4, Pub. American Society of Mechanical Engineers. R. P. Wichner, T D Burchell, and C I Contescu, “Penetration depth and transient oxidation of graphite by oxygen and water”, J. Nucl. Mater. 392 (2009) 518-521 Peter J. Pappano and Timothy D Burchell, Preliminary data on processing and characterization of recycled irradiated graphite, CARBON 48 (2010) 3303-3305 T.D. Burchell and P.J. Pappano, A study of annealing behavior of neutron irradiated graphite, CARBON 49 (2011) 3-10. T.D. Burchell, K.L. Murty, J. Eapen. Irradiation Induced Creep of Graphite, JOM, 62 No. 9 (2010) p. 93-99 T.D. Burchell and P.J. Pappano, Recycling Irradiated Nuclear Graphite – A Greener Path Forward, Proc. 5th International Topical Meeting on High Temperature Reactor Technology (HTR-2010), Oct 18-20, 2010. Paper No. HTR2010-068, In press Nuclear Engineering and Design 251 (2012) 69-77 D.K. Morton, R.I. Jetter, J.E. Nestell, T.D. Burchell, T.-L. (Sam) Sham. SECTION III, DIVISION 5 - DEVELOPMENT AND FUTURE DIRECTIONS, PVP2012-78062. In Proceedings of the ASME


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2012 Pressure Vessels & Piping Division Conference, PVP2012, July 15-19, 2012, Toronto, Ontario, CANADA T. D. Burchell and J. P. Strizak, The Effect of Neutron Irradiation on the Fracture Toughness of Graphite. Proc. HTR 2012, Tokyo, Japan, October 28 – November 1, 2012 (Paper HTR2012-4-004). Also Nuclear Engineering and Design 271 (2014) 262 269

Cristian Contescu, Tyler Guldan, Peng Wang, Timothy Burchell. The Effect of Microstructure on air Oxidation Resistance of Nuclear Graphite, CARBON 50 (2012) 3354-3366 Peng Wang, Cristian Contescu, Suyuan Yu, Timothy D Burchell, Pore structure development in oxidized IG-110 nuclear graphite, Journal of Nuclear Materials 430 (2012) 229-238 Byun, T.S., Li, M., Snead, L.L., Katoh, Y., Burchell, T.D., McDuffee, J.L. Journal of Nuclear Materials Vol. 439, issue 1-3, pp. 108 – 116 (2013) J. Eapen, R. Krishna, T.D. Burchell and K.L. Murty, Early Damage Mechanisms in Nuclear Graphite under Neutron Irradiation, Materials Research Letters, vol. 2, No. 1,pp. 43-50 (2014) Tim Burchell, Joel McDuffee and Ken Thoms, Small Specimen Data from a High Temperature HFIR Irradiation Experiment, American Society for Testing and Material (ASTM) STP 1578 Graphite Testing for Nuclear Applications: The Significance of Test Specimen Volume and Geometry and the Statistical Significance of Test Specimen Population, Pub. ASTM international pp. 172-185 (2014) G Vasudevamurthy, T.S. Byun, P. Pappano, L.L. Snead and T. D. Burchell, Effect of Specimen size and Grain Orientation on the physical properties of NBG-18 Nuclear Graphite Journal of Nuclear Materials 462, pp 1-7 (2015) Timothy D. Burchell and Don Erdman III, The shear fracture toughness, KIIc, of graphite CARBON 98, pp 267-279 (2016) Apu Sarkar Jacob Eapen, Anant Raj, K.L Murty and TD Burchell, Modelling irradiation creep using rate theory Journal of Nuclear Materials 473, pp. 197-205 (2016) Cristian Contescu, Robert Mee Joshua Kane, Nidia Gallego, Timothy Burchell and William Windes, Predictive Model for Chronic Oxidation of Nuclear Graphite under Normal Operating Conditions of High Temperature Gas-Cooled Reactor In Proc. Int. Carbon Conf. PSU, State College, PA. July 10-16. 2016 Timothy D. Burchell and William Windes, A Comparison of the Irradiation Creep Behavior of Several Graphites, In Proc. ANS Winter Meeting 2016, HTR 2016 Embedded Session, Las Vegas, NV, Nov. 6-10, 2016


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IX. BOOK CHAPTERS T. D. Burchell. Radiation Damage in Carbon Materials. In Physical Processes of the Interaction of Fusion Plasmas with Solids. Wolfgang O. Hoffer and Joachim Roth, Editors. Academic Press Inc, pp.341-384, 1996. T. D. Burchell and T. Oku. Materials Properties Data for Fusion Reactor Plasma Facing Carbon-Carbon Composites. IAEA Atomic and Plasma-Material Interaction Data for Fusion (Supplement to the Journal Nuclear Fusion), Vol. 5, pp. 77-128, Dec. 1994. Pub. International Atomic Energy Agency, Vienna, 1994. T. D. Burchell. Fission Reactor Applications of Carbon. In Carbon Materials for Advanced Technologies, T. D. Burchell, Editor. Elsevier Science, Ltd. Oxford (1999). T. D. Burchell. Porous Carbon Fiber-Carbon Binder Composites. In Carbon Materials for Advanced Technologies, T. D. Burchell, Editor. Elsevier Science, Ltd. Oxford (1999). G.R. Romanoski and T. D. Burchell. Fracture in Graphite. In Carbon Materials for Advanced Technologies, T. D. Burchell, Editor. Elsevier Science, Ltd. Oxford (1999). T. D. Burchell. Carbon Materials for Nuclear Energy Applications. In Science of Carbon Materials, Harry Marsh & Francisco Rodriguez Reinoso, Editors. Publicaciones Universidad de Alicante, Spain (2000) T. D. Burchell. Thermal Properties and Nuclear Applications. In Graphite and Precursors (World of Carbon, Vol. 1), Peirre Delhaes, Editor. Gordon & Breach Science Publishers (2001) T. D. Burchell, Carbon Materials for Energy Production and Storage, In. Design and Control of Structure of Advanced Carbon Materials for Enhanced Performance, B. Rand et al (Eds). pp. 277-294, Pub. Kluwer Academic Publishers (2001). T. D. Burchell, Chapter 2.10 Graphite: Properties and Characteristics. In Comprehensive Nuclear Materials, Rudi Konings, Editor. Vol. 2, pp. 285-305, Elsevier Ltd, Oxford (2012). T. D. Burchell, Chapter 4.10 Radiation Effects in Graphite. In Comprehensive Nuclear Materials, Rudi Konings, Editor. Vol. 4, pp.299-324, Elsevier Ltd, Oxford (2012). T.D Burchell, C.I. Contescu and N. C. Gallego, CHAPTER 12 Activated Carbon Fibers for Gas Storage, In Activated Carbon Fibers and Textiles, J. Chen (Ed) pp. XXX-YYY Elsevier Ltd (2017) X BOOKS T. D. Burchell, Editor. Carbon Materials for Advanced Technologies. Elsevier Science, Ltd. Oxford (1999).


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XI. REPORTS A. CEGB reports: TPRD/B/0791/R86 M. O. Tucker, A. P. G. Rose and T.D. Burchell. The

Fracture of Polygrannular Graphites. TPRD/B/0929/R87 A. J. Wickham, T. D. Burchell, P. J. C. Loney, B. Leach and E. A. T. Bowden. Assessment of the 1984 Graphite-

Monitoring Data for Bradwell Reactor No. 2.

TPRD/B/PC/0327/M87 A. J. Wickham and T. D. Burchell. Visit Report: 18th Biennial Conference on Carbon (Worcester, Massachusetts ,19-24 July 1987).

TPRD/B/PC/0328/M87 T. D. Burchell. Visit Report: Oak Ridge National

Laboratory, Tennessee, 28-29 July 1987 (including preliminary discussions on graphite creep held at 21st Carbon Conf Worcester Mass.)

TPRD/B/0997/R87 T. D. Burchell, A. J. Wickham and N. L. Andrews. Irradiation-Induced Dimensional Changes of Pile Grade

"A" Graphite in Magnox Reactors. TPRD/B/1027/R88 T. D. Burchell. The Treatment of Stored Energy and

Thermal Conductivity in the RHASD "Reactor-Heating- After-Shut-Down" Fault Study Code.

TPRD/B/1033/R88 T. D. Burchell, E. Oxley and K. E. Gilchrist. A Review

of Stored Energy in PGA Graphite Irradiated in CEGB Magnox Reactors.

B. ORNL Reports: Letter Report T. D. Burchell. Letter Report on the Fracture Mechanics

Testing of IG-110 Graphite. Milestone Report under US/Japan Agreement on HTGR Technology, Jan 15, 1990 ORNL/NPR-90/18 T. D. Burchell. In "White Paper on Materials for New

Production Reactors", compiled by G. M. Slaughter, Jan.22, 1990.

Letter Report T. D. Burchell. Letter Report on an Improved Carbon-

Carbon Architecture for the General Purpose Heat Source Graphite Impact Shell, transmitted to USDOE, Washington, Jan. 31, 1990.

ORNL/NPR-90/14 T. D. Burchell. A Review of the Properties of Carbon


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Materials suitable for MHTGR High-Temperature Control Rods, June 1990.

ORNL/NPR-90/36 R. W. McClung, D. J. McGuire and T. D. Burchell. Nondestructive Testing for the MHTGR/NPR, Sept. 1990. ORNL/GCR-90/3 E. L. Fuller, Jr., O. C. Kopp, T. D. Burchell and A. D. Underwood. Microgravimetric Analysis of Corrosion of

H-451 Graphite Coolant Impurities: Preliminary Report of Kinetics and Mechanisms, Sept. 1990.

Letter Report T. D. Burchell, C. R. Lutrell and W. F. Jones. Letter

Report on an Improved Carbon-Carbon Composite Graphite Impact Shell, transmitted to USDOE,

Washington, Nov. 1990. ORNL/TM/12047 T. D. Burchell, W. P. Eatherly, G. B. Engle and G. W. Hollenberg. A Carbon-Carbon Composite Development Program For Fusion Energy Applications. July 1991. Oct. 92. ORNL/NPR-91/19 T.D. Burchell, J.P. Strizak, G. Nelson, D. Barker, and J. Bailey. Pre-irradiation Data Report for NPR-MHTGR

Graphite, Irradiation Capsules HTN 1 and 2. Dec. 1991.

ORNL/NPR-91/35 T. D. Burchell, JM Robbins, and J. P. Strizak. Assessment of Post Irradiation Examination Data from HFIR Capsule HTN-1. Dec. 1991.

ORNL/NPR-92/6 T. D. Burchell and J. P. Strizak. Development of Carbon-

Carbon Composite Materials for High-Temperature NP- MHTGR Control Rods. Feb. 1992.

ORNL/NPR-92/32 T. D. Burchell. Graphite Peer Review Plan. Aug. 1992. ORNL/NPR-92/51 T. D. Burchell and JM Robbins. The Thermal Conductivity

of NP-MHTGR Fuel Compacts. Sept. 1993.

ORNL/NPR-92/54 T. D. Burchell. Interim Report on the Thermal Physical Properties of H-451 Graphite. April 1993.

ORNL/NPR-93/7 T. D. Burchell, JM Robbins, and J. P. Strizak. Pre-

Irradiation Data Report for NP-MHTGR Graphite Irradiation Capsule HTN-3. Oct. 1993.

ORNL/NPR-93/10 T. D. Burchell and G. E. Nelson. The Thermal Physical

Properties of H-451 Graphite. Sept. 1993.


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Letter Report T. D. Burchell. A Review of the Pressure Swing Adsorption Process for Gas Separation. June 1994.

Letter Report T. D. Burchell. Modeling the Tensile Failure Probabilities

of High Temperature Engineering Test Reactor Graphites. Sept. 1994.

Letter Report T. D. Burchell, W. P. Eatherly and C. E. Weaver. A

Preliminary Assessment of Carbon Insulation Materials for the ANS Hot Source. August 1995.

ORNL/TM-2001/70 R. D. Carneim, N. C. Gallego, T. D. Burchell and T. R. Armstrong. Desulfurization of Liquid Petroleum Fuels: A Review of Technologies Suitable for On-Board Desulfurization. 2001.

ORNL/TM-2003/289 G.T. Mays, D.G. O’Conner, P.J. Otaduy, R.T. Primm III,

N.C. Gallego, J.C. Conklin, F.C. Difilippo, J.W. Klett, T.D. Burchell, Solid State Reactor Final Report. December 2003

ORNL/TM-2004/182 T. D. Burchell, O. O. Omatete, N. C. Gallego and F. S.

Baker, A Preliminary Assessment of the use of Carbon Fiber Molecular Sieves for Air Separation. September 2004.

ORNL/TM-2005/505 Timothy Burchell and Robert Bratton, Graphite Irradiation

Creep Capsule AGC-1 Experimental Plan, May 2005. ORNL/TM-2005/509 Timothy Burchell and Robert Bratton, Physically Based

Models of the Behavior of Nuclear Graphite under Neutron Irradiation, June 2005.

ORNL/TM-2005/518 T. D. Burchell, L. L. Snead, A. M. Williams, J. L. Bailey,

and J. P. Strizak, Initial Post Irradiation Examination Data Report for SGL NBG-10 Nuclear Grade Graphite, August 2005.

ORNL-GEN4/LTR 05-003 Timothy Burchell, Status of ASTM Subcommittee DO2.F

Graphite Activities, July 2005 ORNL-GEN4/LTR 05-013 Timothy Burchell, Dave Felde, and Ken Thoms,

Experimental Plan and Preliminary Design Report for HFIR High Temperature Graphite Irradiation Capsules HTV-1 and -2. September 2005

ORNL/TM-2006/030 T. D. Burchell, L. L. Snead, A. M. Williams, J. L. Bailey,

and J. P. Strizak, Final Post Irradiation Examination Data Report for SGL NBG-10 Nuclear Grade Graphite, April 2006.


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ORNL/TM-2006/428 Tim Burchell and Rob Bratton, Status of the ASME

Graphite Core Component Project Team’s Activities, March 30, 2006

ORNL/TM-2006/430 T. D. Burchell, L.L. Snead, A.M. Williams, J.L. Bailey, and

J.P. Strizak, Final Post Irradiation Examination Data Report for SGL NBG-10 Nuclear Grade Graphite, April 30, 2006

ORNL/TM-2006/527 Tim Burchell, Terry Yahr, and Rick Battiste, Modeling the

Multiaxial Failure Probability of Nuclear Grade Graphite, June 30, 2006

ORNL-GEN4/LTR-06-015 Cristian Contescu and Tim Burchell, Status of

Development of ASTM D02.F Standard Test Method for Air Oxidation of Graphite, July 30, 2006

ORNL-GEN4/LTR-06-019 T. Burchell, D. Heatherly, J. McDuffee, D. Sparks, and K.

Thoms, Experimental Plan and Final Design Report for High Temperature Graphite Irradiation Capsules HTV-1 and -2, August 31, 2006

ORNL-GEN4/LTR-06-024 T. Burchell, D. Heatherly, J. McDuffee, and K. Thoms,

Preliminary Design Report and Experimental Plan for HFIR Graphite Experimental Creep Capsule HGC-1, August 31, 2006

ORNL-GEN4/LTR-06-023 J.P. Strizak, T.D. Burchell, and W. E. Windes, Status of

Initial Assessment of Physical and Mechanical Properties of Graphite Grades for NGNP Applications, September 5, 2006

ORNL/TM-2006/556 L.L. Snead and T.D. Burchell, Post-Irradiation Examination

of High Temperature Irradiated Nuclear Graphite and Carbon Fiber Composite, September 20, 2006

ORNL/TM-2007/153 T. Burchell, R. Bratton, W. Windes, NGNP Graphite Selection and Acquisition Strategy, September 2007

ORNL/TM-2007/147, Vol. 5 T. Burchell, et al., Next-Generation Nuclear Plant

Phenomena Identification and Ranking Tables (PIRTs)—Volume 5: Graphite PIRTs (NUREG/CR-6944, Vol. 5), 2007

ORNL/TM-2007/228 S.J Ball, T.D. Burchell, W R Corwin, S.E Fisher, C.W. Forsburg, R.N. Morris, and D.L. Mosses. Next Generation Nuclear Plant GAP Analysis Report. Dec. 2008


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ORNL/TM-2008/098 Timothy D. Burchell, Irradiation Induced Creep in Graphite

at high temperature and Dose – A Revised Model, January 2009 ORNL/TM-2008/230 R P Wichner, T D Burchell, and C I Contescu, Note on graphite oxidation by oxygen and moisture, November 2008. ORNL/TM-2009/009 Timothy D. Burchell, A Revised AGC-1 Creep Capsule Layout, January 2009 ORNL/TM-2009/025 Tim Burchell, Steve Nunn, Joe Strizak, and Marie Williams, AGC-1 Sister Specimen Testing Data Report, May 2009 ORNL/TM-2009/026 Rick Battiste, Tim Burchell, and Joe Strizak, The Biaxial Strength of Grade NBG-18 Graphite, September 2009 ORNL/TM-2009/125 Tim Burchell and Joe Strizak, Modeling the Tensile Strength of Grade NBG-18 Graphite, May 2009 ORNL/TM-2009/177 Peter J. Pappano and Timothy D. Burchell, Graphite Recycle - Interim Report on Recycle of Irradiated Graphite Specimens, August 2009 ORNL/TM-2009/192 Cristian I. Contescu and Timothy D. Burchell, Characterization of Porosity Development in Oxidized Graphite using Automated Image Analysis Techniques, August 2009 ORNL/TM-2009/206 Rick Battiste and Tim Burchell, Preliminary Results of Biaxial Strength Testing of NBG-18 Graphite in the Fourth Stress Quadrant, September 2009 ORNL/NRC/LTR-09-01 N C Gallego and T D Burchell, Comparison of NRC Graphite PIRT and DOE Planned Research Activities for Graphite, February 2009 ORNL/NRC/LTR-09-03 N C Gallego, T D Burchell and M. Srinivasan, Milestone Report on the “Workshop on Nuclear Graphite Research”, September 2009 ORNL/GEN4/LTR-09-001 Tim Burchell and Joe Strizak, Experimental Plan for NBG-18 Baseline Characterization, May 2009

ORNL/TM-2010/143 Rick Battiste, Tim Burchell, and Joe Strizak, Biaxial Strength Testing of NBG-18 in the Fourth Stress Quadrant, August 2010


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ORNL/GEN4/LTR/-10-001 Tim Burchell and Yutai Katoh, Development of ASME rules for HTR Applicable Composite Materials - Progress in FY 2010, September 2010

ORNL/TM-2010/169 Tim Burchell and Pete Pappano, The Characterization of

Grade PCEA Recycle Graphite Pilot Scale Billets, August 2010

ORNL/TM-2010/219 Joe Strizak and Tim Burchell, NBG-18 Baseline

Characterization: Billet 6022 635 6 Compressive and Tensile Strengths, September 2010

ORNL/TM-2010/197 Cristian Contescu, Joe Strizak, Tyler Guldan, Tim Burchell.

The Effect of Air Oxidation on Pore Structure Development and Mechanical Properties of Nuclear Graphite, September 2010

ORNL/TM-2010/285 Tim Burchell, Joe Strizak, and Marie Williams. AGC-1 Specimen Pre-irradiation Data Report, October 26, 2010

ORNL/TM-2010/175 Tim Burchell. Modeling the Biaxial Failure of NBG-18 Graphite in the First and Fourth Stress Quadrants, July 1, 2011

ORNL/LTR-2011/86 Tim Burchell. Disassembly of HFIR “Rabbit” Capsules

Containing PCEA Graphite Bars, March 22, 2011

ORNL/TM-2011/175 Tim Burchell. Modeling the Biaxial failure of NBG-18 Graphite in the First and Fourth Stress Quadrants, May 2012

ORNL/TM-2011/472 Cristian Contescu and Timothy Burchell. Initial Test for

Determination of Nuclear Graphite Oxidation Kinetics in Conditions Relevant to VHTR Normal Operation, November 2011

ORNL/TM-2011/497 Tim Burchell and Joe Strizak. Post-Irradiation Examination

Data for PCEA Graphite Irradiated at 900°C in HFIR, May 12, 2012

ORNL/TM-2012/010 Tim Burchell, Joe Strizak, Joel McDuffee and Ken Thoms.

Experimental Plan for HFIR High Temperature Graphite Irradiation Capsule (HTV), April 18, 2012

ORNL/TM-2012/70 Tim Burchell. AGC-1 PIE Experimental Plan, March 2012

ORNL/TM-2012/178 Tim Burchell. AGC-4 Pre-IE Experimental Plan, June 2012


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ORNL/TM-2012/517 Tim Burchell and Joe Strizak, HTV irradiation Capsule

Specimen Pre-IE Report, Feb 2013 ORNL/TM-2013/49 Tim Burchell. Experimental Plan for EDF Energy Creep

Rabbit Graphite Irradiations, April 2013 ORNL/TM-2013/242 Tim Burchell. AGC-1 Post Irradiation Data Report,

September 2013 ORNL/TM-2014/255 Tim Burchell AGC-1 Irradiation Creep Strain Data

Analysis, September 2014 ORNL/TM-2014/614 Tim Burchell and Don Erdman III, The Shear Fracture

Toughness (KIIc) of Graphite’ December 2014 ORNL/TM-2015/142 Cristian Contescu, Timothy Burchell and Robert Mee,

Kinetics of Chronic Oxidation of NBG-17 Nuclear Graphite by Water Vapor, April 2015

ORNL/LTR-2015/155 Tim Burchell, Experimental Plan: Carbon Foam for Beam

Stop Applications May 2015 ORNL/TM-2015/285 Tim Burchell, The Analysis of Results from 3-Point Flexure

Testing of Irradiated Graphite Creep Specimens, February 2016

ORNL/SR-2015/377 Tim Burchell, AGC-1 Irradiation Induced Property Changes

Analysis Report: Electrical Resistivity and Coefficient of Thermal Expansion, February 2016

ORNL/SR-2015/378 Tim Burchell, AGC-1 Irradiation Induced Property Changes

Analysis Report: Dynamic Elastic Modulus, March 2016 ORNL/TM-2015/765 Michael Trammell, Timothy Burchell and Joe Strizak,

PCAE Baseline Characterization: Billet XCP01P8 11 Compressive, Tensile, and Flexure Strengths, December 2015

ORNL/TM-2016/103 Timothy D. Burchell, Wallace D, Porter and Joel L.

McDuffee, The Influence of low dose neutron irradiation on the thermal conductivity of Allcomp carbon foam, March 2016


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C. JAERI Reports: JAERI-memo 07-17 T. D. Burchell and T. Arai. Modeling the Tensile

Fracture Probabilities of Nuclear Graphites with Widely Different Microstructures. JAERI Memo 07-017, February

1995, Pub. Japan Atomic Energy Research Institute.

JAERI-Research 96-016 M. Eto, S. Ishiyama, T. D. Burchell and G. T. Yahr. The Biaxial Strength and Fracture Criteria for HTGR Graphites, JAERI Research Report 96-016. Pub. Japan Atomic Energy Research Institute, March 1996.

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