핵연료 피복관의 산세 공정 시 Nb 함량에 따른 SMUT 특성

문종한; 이영준; 이진행; 홍종원; 이종현; Jong Han Moon; Young Jun Lee; Jin Hang Lee; Jong Won Hong; Jong Hyeon Lee

Korean Journal of Materials Research, Vol.29, No.8, 483-490, August, 2019

DOI10.3740/MRSK.2019.29.8.483 Export Citation

핵연료 피복관의 산세 공정 시 Nb 함량에 따른 SMUT 특성

Evaluation of SMUT Properties according to Nb Content in the Pickling Process of Nuclear Fuel Cladding Tube

문종한^{1, 2}, 이영준³, 이진행¹, 홍종원¹, 이종현^{3, 2, †}

¹한전원자력연료
²충남대학교 신소재공학과
³지론텍

Jong Han Moon^{1, 2}, Young Jun Lee³, Jin Hang Lee¹, Jong Won Hong¹, and Jong Hyeon Lee^{3, 2, †}

¹KEPCO Nuclear Fuel Company, Ltd., Republic of Korea
²Graduate School of Department of Materials Science & Engineering, Chungnam National University, Daejeon 34134, Republic of Korea
³ZironTech Corporation, Republic of Korea

E-mail:

Currently, the Korean nuclear industry uses ZIRLO as material for nuclear fuel cladding(zirconium alloy). KEPCO Nuclear Fuel is in the process of developing a HANA alloy to enable domestic production of cladding. Cladding manufacture involves multistage heat treatments and pickling processes, the latter of which is vital for the removal of defects and impurities on the cladding surface. SMUT that forms on the cladding surface during such pickling process is a source of surface defects during heat treatment and post-treatment processes if not removed. This study analyzes ZIRLO, HANA-4, and HANA-6 alloy claddings to extensively study the SEM/EDS, XRD, and particle size characteristics of SMUT, which are second phase particles that are formed on the cladding surface during pickling processes. Using the analysis results, this study observes SMUT formation characteristics according to Nb concentration in Zr alloys during the washing process following the pickling process. In addition, this study observes SMUT removal characteristics on cladding surfaces according to concentrations of nitric acid and hydrofluoric acid in the acid solution.

Keywords:cladding tube;smut;pickling;zirconium alloy

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[1] Han SK, Nersisyan HH, Lee YJ, Choi JH, Lee JH, Korean J. Mater. Res., 26(12), 681 (2016)

[2] Weidinger HG, in Proceedings of the Water Reactor Systems 7th International Conference on WWER Fuel Performance, Modelling and Experimental Support, Albena, Bulgaria (2007).

[3] Feron D, Nuclear Corrosion Science and Engineering, p.31, Cambridge, Woodhead Publishing Ltd., England (2012).

[4] Garzarolli F, Rudling P, Performance Evaluation of New Advanced Zr Alloys for PWRs/VVERs, p.4, ANT International, Sweden (2011).

[5] Jeong YH, Manufacturing process optimization of nuclear fuel guide HANA alloys, Ministry of Education and Science Technology, KAERI/RR-3195, (2009) from https://inis.iaea.org/collection/NCLCollectionStore/_Public/42/080/42080120.pdf? r=1&r=1.

[6] An CM, Park CH, Kahng JW, Han SK, Lee JH, J. of Korean Inst. of Resources Recycling, 26, 3 (2017).

[7] Hlawka F, Sutter EMM, Werkstoffe und Korrosion, 42, 428 (1991).

[8] McLaughlin DF, Yochum VR, US 2009/0165596 A1 (2009).

[9] Bhattacharjee D, Mandal D, Chem. Technol.: An Indian Journal, 12, 113 (2017).

[10] Bhattacharjee D, Mandal D, in Proceedings of the Indian Institute of Chemical Engineers, (Guwahati, India, December 2015).

[11] Blumenthal WB, J. Am. Chem. Soc., 81, 4759 (1959)

[12] McLaughlin DF, US7468106B2 (2007).

[13] Qiang JB, Zhang W, Xie GQ, Inoue A, J. Mater. Res., 22, 1093 (2007)

[14] Roine A, HSC Chemistry Version 7.11, Outotec, Research Center, Finland.

[15] Ferris LM, J. Chem. Eng. Data, 11, 343 (1966)

[16] Palmieri V, Stivanello F, Stark SY, (The 10th Workshop on RF Superconductivity, Tsukuba, Japan, p.408 2001).

[17] De AK, Inorganic Chemistry and Analysis through Problems and Exercises, p.274, New Age International Private Limited, Delhi (2005).