Effective gaseous diffusion coefficients of select ultra-fine, super-fine and medium grain nuclear graphite

Kane, Joshua J.; Matthews, Austin C.; Orme, Christopher J.; Contescu, Cristian I.; Swank, W. David; Windes, William E.

doi:10.1016/j.carbon.2018.05.003

Effective gaseous diffusion coefficients of select ultra-fine, super-fine and medium grain nuclear graphite

Journal Article · Sat May 05 00:00:00 EDT 2018 · Carbon

DOI:https://doi.org/10.1016/j.carbon.2018.05.003· OSTI ID:1437894

Kane, Joshua J. ^[1]; Matthews, Austin C. ^[1]; Orme, Christopher J. ^[1]; ^[2]; Swank, W. David ^[1]; Windes, William E. ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Understanding “Where?” and “How much?” oxidation has occurred in a nuclear graphite component is critical to predicting any deleterious effects to physical, mechanical, and thermal properties. A key factor in answering these questions is characterizing the effective mass transport rates of gas species in nuclear graphites. Effective gas diffusion coefficients were determined for twenty-six graphite specimens spanning six modern grades of nuclear graphite. A correlation was established for the majority of grades examined allowing a reasonable estimate of the effective diffusion coefficient to be determined purely from an estimate of total porosity. The importance of Knudsen diffusion to the measured diffusion coefficients is also shown for modern grades. Furthermore, Knudsen diffusion has not historically been considered to contribute to measured diffusion coefficients of nuclear graphite.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Energy Efficiency and Renewable Energy (EERE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1437894

Alternate ID(s):: OSTI ID: 1602568
OSTI ID: 1631714

Journal Information:: Carbon, Journal Name: Carbon Journal Issue: C Vol. 136; ISSN 0008-6223

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (35)

Diffusion in a pore of varying cross section Petersen, E. E. AIChE Journal, Vol. 4, Issue 3 https://doi.org/10.1002/aic.690040322	journal	September 1958
Investigation of pore structure by a non-steady-state gas diffusion technique Clark, J. D.; Ghanthan, C. S.; Robinson, P. J. Journal of Materials Science, Vol. 14, Issue 12 https://doi.org/10.1007/BF00611478	journal	December 1979
The effect of diffusion and bulk gas flow on the thermal oxidation of nuclear graphite-I. Temperatures below 500°C Hawtin, P.; Gibson, J. A.; Murdoch, R. Carbon, Vol. 2, Issue 3 https://doi.org/10.1016/0008-6223(64)90044-2	journal	December 1964
The effect of diffusion and bulk gas flow on the thermal oxidation of porous carbons—II. Diffusional effects in graphite at high temperatures Hawtin, P.; Gibson, J. A. Carbon, Vol. 4, Issue 4 https://doi.org/10.1016/0008-6223(66)90064-9	journal	December 1966
The effect of diffusion and bulk gas flow on the thermal oxidation of porous carbons—III. Ungraphitised carbons Hawtin, P.; Gibson, J. A. Carbon, Vol. 4, Issue 4 https://doi.org/10.1016/0008-6223(66)90065-0	journal	December 1966
The effects of non uniform burn off on the kinetics of oxidation of large tubular specimens of graphite Hawtin, P.; Huber, R. A. Carbon, Vol. 6, Issue 6 https://doi.org/10.1016/0008-6223(68)90073-0	journal	December 1968
Air oxidation studies in a long graphite channel Hawtin, P.; Gibson, J. A.; Huber, R. A. Carbon, Vol. 6, Issue 6 https://doi.org/10.1016/0008-6223(68)90074-2	journal	December 1968
The role of in-pore mass transport resistance in the reaction of porous solids with gases The air oxidation of large tubes of graphite Hawtin, P.; Murdoch, R. Chemical Engineering Science, Vol. 19, Issue 10, p. 819-834 https://doi.org/10.1016/0009-2509(64)85093-4	journal	October 1964
Oxidation of P.G.A. graphite by trace mixtures of CO2CO in helium Bourke, P. J.; Gray, M. D.; Denton, W. H. Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology, Vol. 20, Issue 6 https://doi.org/10.1016/0368-3230(66)90092-9	journal	June 1966
The Status of the US High-Temperature Gas Reactors Kadak, Andrew C. Engineering, Vol. 2, Issue 1 https://doi.org/10.1016/J.ENG.2016.01.026	journal	March 2016
Microstructure and molten salt impregnation characteristics of a micro-fine grain graphite for use in molten salt reactors Zhang, Wen-ting; Zhang, Bao-liang; Song, Jin-liang New Carbon Materials, Vol. 31, Issue 6 https://doi.org/10.1016/S1872-5805(16)60034-3	journal	December 2016
The effect of microstructure on air oxidation resistance of nuclear graphite Contescu, Cristian I.; Guldan, Tyler; Wang, Peng Carbon, Vol. 50, Issue 9 https://doi.org/10.1016/j.carbon.2012.01.040	journal	August 2012
An oxygen transfer model for high purity graphite oxidation Kane, Joshua J.; Karthik, Chinnathambi; Ubic, Rick Carbon, Vol. 59 https://doi.org/10.1016/j.carbon.2013.02.053	journal	August 2013
Molten FLiNaK salt infiltration into degassed nuclear graphite under inert gas pressure He, Zhoutong; Gao, Lina; Qi, Wei Carbon, Vol. 84 https://doi.org/10.1016/j.carbon.2014.12.044	journal	April 2015
Experimental study on the oxidation of nuclear graphite and development of an oxidation model Kim, Eung Soo; No, Hee Cheon Journal of Nuclear Materials, Vol. 349, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2005.10.015	journal	February 2006
Comparison of the oxidation rate and degree of graphitization of selected IG and NBG nuclear graphite grades Chi, Se-Hwan; Kim, Gen-Chan Journal of Nuclear Materials, Vol. 381, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2008.07.027	journal	October 2008
A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP) Pappano, P. J.; Burchell, T. D.; Hunn, J. D. Journal of Nuclear Materials, Vol. 381, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2008.07.032	journal	October 2008
Development and validation of a model for the chemical kinetics of graphite oxidation El-Genk, Mohamed S.; Tournier, Jean-Michel P. Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.129	journal	April 2011
Comparison of oxidation model predictions with gasification data of IG-110, IG-430 and NBG-25 nuclear graphite El-Genk, Mohamed S.; Tournier, Jean-Michel P. Journal of Nuclear Materials, Vol. 420, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.09.027	journal	January 2012
Oxidation rate of nuclear-grade graphite NBG-18 in the kinetic regime for VHTR air ingress accident scenarios Lee, Jo Jo; Ghosh, Tushar K.; Loyalka, Sudarshan K. Journal of Nuclear Materials, Vol. 438, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.002	journal	July 2013
Chemical kinetics parameters and model validation for the gasification of PCEA nuclear graphite El-Genk, Mohamed S.; Tournier, Jean-Michel P.; Contescu, Cristian I. Journal of Nuclear Materials, Vol. 444, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.031	journal	January 2014
Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios Lee, Jo Jo; Ghosh, Tushar K.; Loyalka, Sudarshan K. Journal of Nuclear Materials, Vol. 446, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.11.032	journal	March 2014
Oxidation of PCEA nuclear graphite by low water concentrations in helium Contescu, Cristian I.; Mee, Robert W.; Wang, Peng Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.009	journal	October 2014
The relationship between microstructure and oxidation effects of selected IG- and NBG-grade nuclear graphites Huang, Wei-Hao; Tsai, Shuo-Cheng; Yang, Chia-Wei Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.052	journal	November 2014
Irradiation testing of matrix material for spherical HTR-10 fuel elements Tang, Chunhe; Li, Ziqiang; Zou, Yanwen Nuclear Engineering and Design, Vol. 238, Issue 11 https://doi.org/10.1016/j.nucengdes.2008.01.021	journal	November 2008
Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR Hinssen, Hans-Klemens; Kühn, Kerstin; Moormann, Rainer Nuclear Engineering and Design, Vol. 238, Issue 11 https://doi.org/10.1016/j.nucengdes.2008.02.013	journal	November 2008
The oxidation effects of nuclear graphite during air-ingress accidents in HTGR Huang, Wei-Hao; Tsai, Shuo-Cheng; Chiu, I-Che Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.11.047	journal	May 2014
Interdiffusion of Helium and Argon in a Large-Pore Graphite. Evans, R. B.; Truitt, Jack; Watson, G. M. Journal of Chemical & Engineering Data, Vol. 6, Issue 4 https://doi.org/10.1021/je60011a012	journal	October 1961
Gaseous Diffusion in Porous Media with Particular Reference to Graphite Hewitt, G. F.; Sharratt, E. W. Nature, Vol. 198, Issue 4884 https://doi.org/10.1038/198952a0	journal	June 1963
Gaseous Diffusion Coefficients Marrero, T. R.; Mason, E. A. Journal of Physical and Chemical Reference Data, Vol. 1, Issue 1 https://doi.org/10.1063/1.3253094	journal	January 1972
Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite Marsden, B. J.; Haverty, M.; Bodel, W. International Materials Reviews, Vol. 61, Issue 3 https://doi.org/10.1080/09506608.2015.1136460	journal	April 2016
Analysis of Combustion Kinetics of Powdered Nuclear Graphite by using a Non-isothermal Thermogravimetric Method Yang, Hee-Chul; Eun, Hee-Chul; Lee, Dong-Gyu Journal of Nuclear Science and Technology, Vol. 43, Issue 11 https://doi.org/10.1080/18811248.2006.9711238	journal	November 2006
Recommendations for the characterization of porous solids (Technical Report) Rouquerol, J.; Avnir, D.; Fairbridge, C. W. Pure and Applied Chemistry, Vol. 66, Issue 8, p. 1739-1758 https://doi.org/10.1351/pac199466081739	journal	January 1994
Diffusion Slip Velocity: Theory and Experiment Lang, H.; Loyalka, S. Zeitschrift für Naturforschung A, Vol. 27, Issue 8-9 https://doi.org/10.1515/zna-1972-8-926	journal	September 1972
Effects of Porosity and Temperature on Oxidation Behavior in Air of Selected Nuclear Graphites Chen, Dongyue; Li, Zhengcao; Miao, Wei MATERIALS TRANSACTIONS, Vol. 53, Issue 6 https://doi.org/10.2320/matertrans.MBW201107	journal	January 2012

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Investigation on the oxidation behavior and multi-step reaction mechanism of nuclear graphite SNG742 Lu, Wei; Li, Xiaowei; Wu, Xinxin Journal of Nuclear Science and Technology, Vol. 57, Issue 3 https://doi.org/10.1080/00223131.2019.1671910	journal	September 2019

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