Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength
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...
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Language: | English |
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Wiley
2017-01-01
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Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2017/4275375 |
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author | Xiangwen Zhou Cristian I. Contescu Xi Zhao Zhenming Lu Jie Zhang Yutai Katoh Yanli Wang Bing Liu Yaping Tang Chunhe Tang |
author_facet | Xiangwen Zhou Cristian I. Contescu Xi Zhao Zhenming Lu Jie Zhang Yutai Katoh Yanli Wang Bing Liu Yaping Tang Chunhe Tang |
author_sort | Xiangwen Zhou |
collection | DOAJ |
description | 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. |
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language | English |
publishDate | 2017-01-01 |
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series | Science and Technology of Nuclear Installations |
spelling | doaj-art-1f083c396d764f89b6e28954d8f53cbc2025-02-03T05:46:02ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/42753754275375Oxidation Behavior of Matrix Graphite and Its Effect on Compressive StrengthXiangwen Zhou0Cristian I. Contescu1Xi Zhao2Zhenming Lu3Jie Zhang4Yutai Katoh5Yanli Wang6Bing Liu7Yaping Tang8Chunhe Tang9Institute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaOak Ridge National Laboratory, UT-Battelle Inc., P.O. Box 2008, Oak Ridge, TN 37831, USAInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaOak Ridge National Laboratory, UT-Battelle Inc., P.O. Box 2008, Oak Ridge, TN 37831, USAOak Ridge National Laboratory, UT-Battelle Inc., P.O. Box 2008, Oak Ridge, TN 37831, USAInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, ChinaMatrix 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.http://dx.doi.org/10.1155/2017/4275375 |
spellingShingle | Xiangwen Zhou Cristian I. Contescu Xi Zhao Zhenming Lu Jie Zhang Yutai Katoh Yanli Wang Bing Liu Yaping Tang Chunhe Tang Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength Science and Technology of Nuclear Installations |
title | Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength |
title_full | Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength |
title_fullStr | Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength |
title_full_unstemmed | Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength |
title_short | Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength |
title_sort | oxidation behavior of matrix graphite and its effect on compressive strength |
url | http://dx.doi.org/10.1155/2017/4275375 |
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