Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength
Abstract
Matrix graphite (MG) with incompletely graphitized binder used in high-temperature gas-cooled reactors (HTGRs) is commonly suspected to exhibit lower oxidation resistance in air. In order to reveal the oxidation performance, the oxidation behavior of newly developed A3-3 MG at the temperature range from 500 to 950°C in air was studied and the effect of oxidation on the compressive strength of oxidized MG specimens was characterized. Results show that temperature has a significant influence on the oxidation behavior of MG. The transition temperature between Regimes I and II is ~700°C and the activation energy ( ) in Regime I is around 185 kJ/mol, a little lower than that of nuclear graphite, which indicates MG is more vulnerable to oxidation. Oxidation at 550°C causes more damage to compressive strength of MG than oxidation at 900°C. Comparing with the strength of pristine MG specimens, the rate of compressive strength loss is 77.3% after oxidation at 550°C and only 12.5% for oxidation at 900°C. Microstructure images of SEM and porosity measurement by Mercury Porosimetry indicate that the significant compressive strength loss of MG oxidized at 550°C may be attributed to both the uniform pore formation throughout the bulk and the preferential oxidation of the binder.
- Authors:
-
[1];
[1];
- Institute of Nuclear and New Energy Technology of Tsinghua Univ., Beijing (China)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1399943
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Science and Technology of Nuclear Installations
- Additional Journal Information:
- Journal Volume: 2017; Journal ID: ISSN 1687-6075
- Publisher:
- Hindawi
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Citation Formats
Zhou, Xiangwen, Contescu, Cristian I., Zhao, Xi, Lu, Zhenming, Zhang, Jie, Katoh, Yutai, Wang, Yanli, Liu, Bing, Tang, Yaping, and Tang, Chunhe. Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength. United States: N. p., 2017.
Web. doi:10.1155/2017/4275375.
Zhou, Xiangwen, Contescu, Cristian I., Zhao, Xi, Lu, Zhenming, Zhang, Jie, Katoh, Yutai, Wang, Yanli, Liu, Bing, Tang, Yaping, & Tang, Chunhe. Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength. United States. https://doi.org/10.1155/2017/4275375
Zhou, Xiangwen, Contescu, Cristian I., Zhao, Xi, Lu, Zhenming, Zhang, Jie, Katoh, Yutai, Wang, Yanli, Liu, Bing, Tang, Yaping, and Tang, Chunhe. Sun .
"Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength". United States. https://doi.org/10.1155/2017/4275375. https://www.osti.gov/servlets/purl/1399943.
@article{osti_1399943,
title = {Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength},
author = {Zhou, Xiangwen and Contescu, Cristian I. and Zhao, Xi and Lu, Zhenming and Zhang, Jie and Katoh, Yutai and Wang, Yanli and Liu, Bing and Tang, Yaping and Tang, Chunhe},
abstractNote = {Matrix graphite (MG) with incompletely graphitized binder used in high-temperature gas-cooled reactors (HTGRs) is commonly suspected to exhibit lower oxidation resistance in air. In order to reveal the oxidation performance, the oxidation behavior of newly developed A3-3 MG at the temperature range from 500 to 950°C in air was studied and the effect of oxidation on the compressive strength of oxidized MG specimens was characterized. Results show that temperature has a significant influence on the oxidation behavior of MG. The transition temperature between Regimes I and II is ~700°C and the activation energy (Ea) in Regime I is around 185 kJ/mol, a little lower than that of nuclear graphite, which indicates MG is more vulnerable to oxidation. Oxidation at 550°C causes more damage to compressive strength of MG than oxidation at 900°C. Comparing with the strength of pristine MG specimens, the rate of compressive strength loss is 77.3% after oxidation at 550°C and only 12.5% for oxidation at 900°C. Microstructure images of SEM and porosity measurement by Mercury Porosimetry indicate that the significant compressive strength loss of MG oxidized at 550°C may be attributed to both the uniform pore formation throughout the bulk and the preferential oxidation of the binder.},
doi = {10.1155/2017/4275375},
journal = {Science and Technology of Nuclear Installations},
number = ,
volume = 2017,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2017},
month = {Sun Jan 01 00:00:00 EST 2017}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 6 works
Citation information provided by
Web of Science
Web of Science
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
Oxidation rate of graphitic matrix material in the kinetic regime for VHTR air ingress accident scenarios
journal, August 2014
- Lee, Jo Jo; Ghosh, Tushar K.; Loyalka, Sudarshan K.
- Journal of Nuclear Materials, Vol. 451, Issue 1-3
Penetration depth and transient oxidation of graphite by oxygen and water vapor
journal, September 2009
- Wichner, Robert P.; Burchell, Timothy D.; Contescu, Cristian I.
- Journal of Nuclear Materials, Vol. 393, Issue 3
Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR
journal, November 2008
- Hinssen, Hans-Klemens; Kühn, Kerstin; Moormann, Rainer
- Nuclear Engineering and Design, Vol. 238, Issue 11
Current status and technical description of Chinese 2×250MWth HTR-PM demonstration plant
journal, July 2009
- Zhang, Zuoyi; Wu, Zongxin; Wang, Dazhong
- Nuclear Engineering and Design, Vol. 239, Issue 7
Effects of air flow rate on the oxidation of NBG-18 and NBG-25 nuclear graphite
journal, August 2017
- Chi, Se-Hwan; Chan Kim, Gen
- Journal of Nuclear Materials, Vol. 491
Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite
journal, February 2004
- Moormann, Rainer; Hinssen, Hans-Klemens; Kühn, Kerstin
- Nuclear Engineering and Design, Vol. 227, Issue 3
Preparation of spherical fuel elements for HTR-PM in INET
journal, October 2013
- Xiangwen, Zhou; Zhenming, Lu; Jie, Zhang
- Nuclear Engineering and Design, Vol. 263
Oxidation behavior of IG and NBG nuclear graphites
journal, January 2011
- Choi, Woong-Ki; Kim, Byung-Joo; Kim, Eung-Seon
- Nuclear Engineering and Design, Vol. 241, Issue 1
Practical aspects for characterizing air oxidation of graphite
journal, October 2008
- Contescu, Cristian I.; Azad, Samina; Miller, Doug
- Journal of Nuclear Materials, Vol. 381, Issue 1-2
Comparison of Oxidation Behaviors of Different Grades of Nuclear Graphite
journal, September 2005
- Luo, Xiaowei; Robin, Jean-Charles; Yu, Suyuan
- Nuclear Science and Engineering, Vol. 151, Issue 1
Works referencing / citing this record:
Investigation on the oxidation behavior and multi-step reaction mechanism of nuclear graphite SNG742
journal, September 2019
- Lu, Wei; Li, Xiaowei; Wu, Xinxin
- Journal of Nuclear Science and Technology, Vol. 57, Issue 3