Effects of Porosity and Temperature on Oxidation Behavior in Air of Selected Nuclear Graphites
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- Chen Dongyue
- State Key Laboratory of New Ceramic and Fine Processing, Department of Materials Science and Engineering, Tsinghua University
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- Li Zhengcao
- State Key Laboratory of New Ceramic and Fine Processing, Department of Materials Science and Engineering, Tsinghua University
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- Miao Wei
- State Key Laboratory of New Ceramic and Fine Processing, Department of Materials Science and Engineering, Tsinghua University
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- Zhang Zhengjun
- State Key Laboratory of New Ceramic and Fine Processing, Department of Materials Science and Engineering, Tsinghua University
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抄録
Nuclear graphite endures gas oxidation in High Temperature Gas-cooled Reactor (HTGR), which may threaten the safety of reactor. To study the oxidation behavior of nuclear graphite, weight loss curve is usually measured through Thermo Gravimetric Analysis (TGA) method. In this work, three brands of nuclear graphite for HTGR (i.e., HSM-SC, IG-11, and NBG-18) are oxidized under 873 and 1073 K in open air, and their weight loss curves are obtained. The acceleration of oxidizing rate is observed for both HSM-SC and IG-11, and is attributed to the large porosity increase during oxidation process. For HSM-SC, the porosity increase comes from preferential binder oxidation, and thus its binder quality shall be improved to obtain better oxidation resistance. Temperature effects on oxidation for HSM-SC are also studied, which shows that oxidizing gas tends to be exhausted at graphite surface at high temperature instead of penetrate into the interior of bulk.
収録刊行物
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- MATERIALS TRANSACTIONS
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MATERIALS TRANSACTIONS 53 (6), 1159-1163, 2012
公益社団法人 日本金属学会
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詳細情報 詳細情報について
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- CRID
- 1390001204249972480
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- NII論文ID
- 10030630358
- 130004824884
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- NII書誌ID
- AA1151294X
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- ISSN
- 13475320
- 13459678
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- NDL書誌ID
- 023682526
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- NDL
- Crossref
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- 使用不可