Search Results - "Burchell, Timothy D."

A Review of Finite Element Method Models for Nuclear Graphite Applications.

Authors: Arregui-Mena, José David Worth, Robert N. Hall, Graham et al.

Source: Archives of Computational Methods in Engineering; Jan2020, Vol. 27 Issue 1, p331-350, 20p

CHAPTER 3: Carbon Materials for Nuclear Energy Applications.

Authors: Burchell, Timothy D.¹

Source: Sciences of Carbon Materials. 2000, p117-147. 31p. 5 Diagrams, 5 Charts, 6 Graphs.

The shear fracture toughness, KIIc, of graphite.

Authors: Burchell, Timothy D. Erdman, Don

Source: Carbon. Mar2016, Vol. 98, p267-279. 13p.

Subjects: Fracture toughness, Shearing force, Graphite, Acoustic emission, Mechanical loads

Leveraging comprehensive baseline datasets to quantify property variability in nuclear-grade graphites.

Authors: Carroll, Mark C. Windes, William E. Rohrbaugh, David T. et al.

Source: Nuclear Engineering & Design; Oct2016, Vol. 307, p77-85, 9p

Penetration depth and transient oxidation of graphite by oxygen and water vapor

Authors: Wichner, Robert P. Burchell, Timothy D. Contescu, Cristian I.

Source: Journal of Nuclear Materials. Sep2009, Vol. 393 Issue 3, p518-521. 4p.

Subjects: Chemical kinetics, Oxidation, Graphite, Estimates, Temperature effect, Atmospheric water vapor, Chemical equilibrium

Irradiation induced creep behavior of H-451 graphite

Authors: Burchell, Timothy D.¹ burchelltd@ornl.gov

Source: Journal of Nuclear Materials. Oct2008, Vol. 381 Issue 1/2, p46-54. 9p.

Subjects: Irradiation, Creep (Materials), Graphite

The effect of neutron irradiation damage on the properties of grade NBG-10 graphite

Authors: Burchell, Timothy D. Snead, Lance L.

Source: Journal of Nuclear Materials. Sep2007, Vol. 371 Issue 1-3, p18-27. 10p.

Subjects: Materials, Nuclear science, Physical sciences, Nuclear physics

Irradiation effects on graphite foam

Authors: Gallego, Nidia C. Burchell, Timothy D. Klett, James W.

Source: Carbon. Apr2006, Vol. 44 Issue 4, p618-628. 11p.

Subjects: Irradiation, Heat transfer, Graphite, Foam, Thermal properties

Density Change of an Oxidized Nuclear Graphite by Acoustic Microscopy and Image Processing.

Authors: Chi, Se-Hwan Contescu, Cristian I. Burchell, Timothy D.

Source: Journal of Engineering for Gas Turbines & Power; September 2009, Vol. 131 Issue 5, p052904-052904, 1p

Preliminary data on processing and characterization of recycled irradiated graphite

Authors: Pappano, Peter J. Burchell, Timothy D.

Source: Carbon. Sep2010, Vol. 48 Issue 11, p3303-3305. 3p.

Subjects: Graphite, Filler materials, Feasibility studies, Particle size distribution, Radiology, Temperature effect

Density Change of an Oxidized Nuclear Graphite by Acoustic Microscopy and Image Processing.

Authors: Se-Hwan Chi Contescu, Cristian I. Burchell, Timothy D.

Source: Journal of Engineering for Gas Turbines & Power. Sep2009, Vol. 131 Issue 5, p052904:1-052904:4. 4p. 4 Graphs.

Subjects: Graphite, Acoustic microscopy, Image processing, High temperatures, Electric power production, Gas engineering

Beyond the classical kinetic model for chronic graphite oxidation by moisture in high temperature gas-cooled reactors.

Authors: Contescu, Cristian I. Mee, Robert W. Lee, Yoonjo (jo Jo) et al.

Source: Carbon. Feb2018, Vol. 127, p158-169. 12p.

Oxidation of PCEA nuclear graphite by low water concentrations in helium.

Authors: Contescu, Cristian I. Mee, Robert W. Peng Wang et al.

Source: Journal of Nuclear Materials. Oct2014, Vol. 453 Issue 1-3, p225-232. 8p.

Principles and practice of a bellows-loaded compact irradiation vehicle.

Authors: Byun, Thak Sang Li, Meimei Snead, Lance L. et al.

Source: Journal of Nuclear Materials. Aug2013, Vol. 439 Issue 1-3, p108-116. 9p.

Pore structure development in oxidized IG-110 nuclear graphite

Authors: Wang, Peng Contescu, Cristian I. Yu, Suyuan et al.

Source: Journal of Nuclear Materials. Nov2012, Vol. 430 Issue 1-3, p229-238. 10p.

The effect of microstructure on air oxidation resistance of nuclear graphite

Authors: Contescu, Cristian I. Guldan, Tyler Wang, Peng et al.

Source: Carbon. Aug2012, Vol. 50 Issue 9, p3354-3366. 13p.

Practical aspects for characterizing air oxidation of graphite

Authors: Contescu, Cristian I. Azad, Samina Miller, Doug et al.

Source: Journal of Nuclear Materials. Oct2008, Vol. 381 Issue 1/2, p15-24. 10p.

Selection of water-dispersible carbon black for fabrication of uranium oxicarbide microspheres

Authors: Contescu, Cristian I. Baker, Frederick S. Hunt, Rodney D. et al.

Source: Journal of Nuclear Materials. Mar2008, Vol. 375 Issue 1, p38-51. 14p.

Effects of heat treatment conditions on the thermal properties of mesophase pitch-derived graphitic foams

Authors: Klett, James W. McMillan, April D. Gallego, Nidia C. et al.

Source: Carbon. Aug/Sep2004, Vol. 42 Issue 8/9, p1849-1852. 4p.

Protection of graphite from salt and gas permeation in molten salt reactors.

Authors: Lee, Jo Jo Arregui-Mena, José D. Contescu, Cristian I. et al.

Source: Journal of Nuclear Materials. Jun2020, Vol. 534, pN.PAG-N.PAG. 1p.