References
- F. I. VALENTIN et al., “Study of Convection Heat Transfer in a Very High Temperature Reactor Flow Channel: Numerical and Experimental Results,” Nucl. Technol., 196, 661 (2016); https://doi.org/10.13182/NT16-46.
- TOKAI CARBON USA, “Fine/Ultra Fine Grain Isostatic Graphite,” Tokai Carbon website; http://tokaicarbon.com/fine_carbon_products/isostatic_graphite-ultra_fine_grain.html ( current as of May 9, 2017).
- G. L. WESSMAN, “Safety Analysis Report: Use of H-451 Graphite in Fort St. Vrain Fuel Elements,” GLP-5588, General Atomics (1977).
- F. H. HO, “Graphite Design Handbook,” Report DOE-HTGR-88111, General Atomics, San Diego, California (1988).
- R. J. PRICE, “Review of the Thermal Conductivity of Nuclear Graphite Under HTGR Conditions,” Technical report Gulf-GA-A12615, Gulf General Atomic Company, San Diego, California (Sep. 7, 1973).
- H. O. PIERSON, Handbook of Carbon, Graphite, Diamonds and Fullerenes, Noyes Publications, Park Ridge, New Jersey (1993).
- E. ITKIN, Electronic Personal Communication, Graphite Store (Jan. 26, 2017).
- W. D. SWANK et al., “Carbon Characterization Laboratory Report,” INL/EXT-09-15515, Idaho National Laboratory (Mar. 2009); www.osti.gov/servlets/purl/950990 ( current as of Dec. 1, 2016).
- ASTM C781-08(2014), “Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components,” ASTM International, West Conshohocken, Pennsylvania (2014).
- D. M. McELIGOT et al., “Thermal Properties of G-348 Graphite,” INL/EXT-16-38241, Revision 1, Idaho National Laboratory (Apr. 2017); www.osti.gov/scitech/; OSTI ID 1355904.
- ASTM C559-90 (2005), “Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles,” ASTM International, West Conshohocken, Pennsylvania (2005).
- ASTM E228-06, “Standard Test Method for Linear Thermal Expansion of Solid Materials with a Push-Rod Dilatometer,” ASTM International, West Conshohocken, Pennsylvania (2006).
- ASTM E1461-07, “Standard Test Method for Thermal Diffusivity by the Flash Method,” ASTM International, West Conshohocken, Pennsylvania (2007).
- ASTM E2585-09, “Standard Practice for Thermal Diffusivity by the Flash Method,” ASTM International, West Conshohocken, Pennsylvania (2009).
- J. H. KIM, T. W. SIMON, and R. VISKANTA, “Journal of Heat Transfer Policy on Reporting Uncertainties in Experimental Measurements and Results,” J. Heat Transfer, 115, 5 (1993); https://doi.org/10.1115/1.2910670.
- S. J. KLINE and F. A. McCLINTOCK, “Describing Uncertainties in Single-Sample Experiments,” Mech. Eng., 75, 3 (Jan. 1955).
- R. J. MOFFAT, “Contributions to the Theory of Single-Sample Uncertainty Analysis,” J. Fluids Eng., 104, 250 (1982); https://doi.org/10.1115/1.3241818.
- R. J. MOFFAT, “Describing the Uncertainties in Experimental Results,” Exp. Thermal Fluid Sci., 1, 3 (1988); https://doi.org/10.1016/0894-1777(88)90043-X.
- S. J. KLINE, “The Purposes of Uncertainty Analysis,” J. Fluids Eng., 107, 153 (1985); https://doi.org/10.1115/1.3242449.
- J. R. TAYLOR, An Introduction to Error Analysis, 2nd ed., p. 135, University Science Books, Sausalito, California (1997).
- Mechanical Engineers’ Handbook, 1st ed., L. S. MARKS, Ed., p. 293, McGraw-Hill, New York (1916).
- G. MELESE and R. KATZ, Thermal and Flow Design of Helium-Cooled Reactors, American Nuclear Society, La Grange Park, Illinois (1984).
- A. T. D. BUTLAND and R. J. MADDISON, “The Specific Heat of Graphite: An Evaluation of Measurements,” J. Nucl. Mater., 49, 45 (1973/4); https://doi.org/10.1016/0022-3115(73)90060-3.
- W. N. REYNOLDS, Physical Properties of Graphite, Elsevier, Amsterdam (1968).
- B. T. KELLY, “Thermal Conductivity of Graphite,” Chemistry and Physics of Carbons, Vol. 5, p. 119, Marcel Decker, Inc., New York (1969).
- R. TAYLOR, “The Thermal Conductivity of Pyrolytic Graphite,” Phil. Mag., 13, 121, 157 (1966); https://doi.org/10.1080/14786436608211993.
- R. J. PRICE, “Thermal Conductivity of Neutron-Irradiated Reactor Graphites,” Carbon, 13, 201 (1975); https://doi.org/10.1016/0008-6223(75)90232-8.
- S. GLASSTONE, Principles of Nuclear Reactor Engineering, D. van Nostrand, Princeton, New Jersey (1955).