원자로급 흑연 IG-11의 산화율에 따른 기공도와 열방사율과의 관계

서승국; 노재승; 김경화; 지세환; 김응선; Seung-Kuk Seo; Jae-Seung Roh; Gyeong-Hwa Kim; Se-Hwan Chi; Eung-Seon Kim

Korean Journal of Materials Research, Vol.18, No.12, 645-649, December, 2008

DOI10.3740/MRSK.2008.18.12.645 Export Citation

원자로급 흑연 IG-11의 산화율에 따른 기공도와 열방사율과의 관계

Correlation Between the Porosity and the Thermal Emissivity as a Function of Oxidation Degrees on Nuclear Graphite IG-11

서승국, 노재승 ^†, 김경화, 지세환¹, 김응선¹

금오공과대학교 신소재시스템공학부
¹한국원자력연구소

Seung-Kuk Seo, Jae-Seung Roh^†, Gyeong-Hwa Kim, Se-Hwan Chi¹, and Eung-Seon Kim¹

School of Advanced Materials and Systems Engineering, Kumoh National Institute of Technology, Gumi, Gyeongbuk 730-701, Korea
¹Korea Atomic Energy Research Institute (KAERI), Yuseong-gu, Daejeon 305-353, Korea

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Graphite for the nuclear reactor is used to the moderator, reflector and supporter in which fuel rod inside of nuclear reactor. Recently, there are many researches has been performed on the various characteristics of nuclear graphite, however most of them are restricted to the structural and the mechanical properties. Therefore we focused on the thermal property of nuclear graphite. This study investigated the thermal emissivity following the oxidation degree of nuclear graphite with IG-11 used as a sample. IG-11 was oxidized to 6 % and 11 % in air at 5 l/min at 600 oC. The porosity and thermal emissivity of the sample were measured using a mercury porosimeter and by an IR method, respectively. The thermal emissivity of an oxidized sample was measured at 100 oC, 200 oC, 300 oC, 400 oC and 500 oC. The porosity of the oxidized samples was found to increase as the oxidation degree increased. The thermal emissivity increased as the oxidation degree increased, and the thermal emissivity decreased as the measured temperature increased. It was confirmed that the thermal emissivity of oxidized IG-11 is correlated with the porosity of the sample.

Keywords:thermal emissivity;nuclear graphite IG-11;oxidation degrees;porosity

[References]

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Bellayer S, Gilman JW, Rahatekar SS, Bourbigot S, Flambard X, Hanssen LM, Guo H, Kumar S, Carbon, 45, 2417 (2007)

[Related Articles]

[1] Mitchell BC, Smart J, Fok SL, Marsden BJ, J. Nucl. Mater., 322, 126 (2003)

[2] Kurumada A, Oku T, Harada K, Kawamata K, Sato S, Hiraoka T, McEaney B, Carbon, 35(8), 1157 (1997)

[3] Moormann R, Hinssen HK, Kuhn K, Nucl. Eng. Des., 227, 281 (2004)

[4] Loren Fuller E, Okoh JM, J. Nucl. Mater., 240, 241 (1997)

[5] Chunhe T, Jie G, J. Nucl. Mater., 224, 103 (1995)

[6] Rainer M, Hinssen HK, Kerstin K, Nucl. Eng. Des., 227, 281 (2004)

[7] Xiaowei L, Suyuan Y, Xuanyu S, Shuyan H, Nucl. Eng. Des., 235, 2261 (2005)

[8] Cho GY, Kim GJ, Lim YS, Jung YJ, Chi SH, J. Kor. Ceram. Soc., 43(12), 833 (2006)

[9] Bellayer S, Gilman JW, Rahatekar SS, Bourbigot S, Flambard X, Hanssen LM, Guo H, Kumar S, Carbon, 45, 2417 (2007)