Nb 첨가량에 따른 Zr-O.8Sn-xNb 3원계 합금의 미세조직 및 부식특성 연구

검현길; 정용환; 위명용; Hyun Gil Kim; Yong Hwan Jeong; Myung Yong Wey

Korean Journal of Materials Research, Vol.9, No.5, 452-459, May, 1999

Export Citation

Nb 첨가량에 따른 Zr-O.8Sn-xNb 3원계 합금의 미세조직 및 부식특성 연구

Study on Microstructure and Corrosion Characteristics of Zr-O.8Sn-xNb Ternary Alloys

검현길, 정용환¹, 위명용

충북대학교 재료공학과
¹한국원자력연구소 핵연료피복관개발과제

Hyun Gil Kim, Yong Hwan Jeong¹, and Myung Yong Wey

Dept. of Materials Engineering, Chung Buk National University, Cheong Ju 361-763, Korea
¹Development of Advanced Cladding Materials, Korea Atomic Energy Research Institute, Taejon 305-353, Korea

초록

고연소도 핵연료피복관용 신합금 채료흘 개발하기 위한 연구로 Zr-0.8Sn-xNb(x = 0.2, 0.4, 0.8, 1.0) 계 합금을 제조하여 Nb 첨가량이 Zr 합금의 미세구조 빛 부식특성에 미치는 영향을 조사하였다. 미세조직 관찰결과 Nb첨가량이 중가함에 따라 결청럽의 크기는 감소하였고 석출물의 량은 증가하였다. 360 ℃ 물분위기에서 부식시험 한 결과 Nb 함량이 적을수록 부식저항성이 증가하는 경향을 나타냈으며, Zr-0.8Sn-0.2Nb 합금이 가장 우수한 부식저항성을 보였다. 동일 두께의 산화막에 대하여 XRD 분석한 결과, 내식성이 우수한 0.2 wt.% Nb 합금에서는 산화막내 tetra-ZrO2의 분율이 높게 관찰되었다. 합금설계 관점에서 Zr-O.8Sn-xNb 합금계에 Nb을 첨가할때 Nb은 고용도 이하로 첨가되어야 한다고 사료된다.

To develop advanced cladding materials, the effect of Nb addition on the microstructure and corrosion characteristics of Zr-0.8Sn-xNb alloys was investigated. As the Nb content increased, the grain size decreased and the volume fraction of precipitates increased. It was observed from the corrosion test at 360℃ that the corrosion resistance increased with decreasing Nb ∞ntent. The best corrosion resistance was obtained in Zr-0.8Sn-0.2Nb alloy with high volume fraction of tetra-ZrO2, in the oxide. Therefore, it is suggested that Nb in the Zr-0.8Sn-xNb system should be added within the solubility limit of Nb from the viewpoint of alloy design.

[References]

Sabol GP, Kilp GR, Balfour MG, Roberts E, Zirconium in the Nuclear Industry, ASTM STP 1023 (1989) 227.
Yamate K, Oe A, Hayashi M, Okamoto T, Anada H, Hagi S, Amer. Nucl. Soci., 318 (1997)
Mardon JP, Garner G, Beslu P, CharQuet D, Senevat J, Amer. Nucl. Soci, 405 (1997)
연영명, 정용환, 위명용, 대한금속학회지, 35, 1576 (1997)
정용환, 한국재료학회지, 6, 585 (1996)
Isobe T, Matsuo Y, ASTM STP, 1132, 346 (1991)
Urbanic VF, Gilbert RW, IAEA Technical CommitteeMeeting on Fundamental Aspects of Corrosion of Zr-base Alloys for Water Reactor Enviroments, Portland, Oregon, 11-15 Sept. (1989)
Godlewski J, ASTM STP, 1245, 663 (1994)
Garzarolli F, Seidel H, Tricot R, Gros JP, ASTM STP, 1132, 395 (1991)
Anada H, Herb BJ, Nomoto K, Hagi S, Graham RA, Kuroda T, ASTM STP, 1295, 74 (1996)
Beie HJ, Mitwalsky A, Garzarolli F, Ruhmann H, Sell HJ, ASTM STP, 1245, 615 (1994)
Jeong YH, Beak JH, Kim SJ, Kim HG, Ruhmann H, J. Nucl. Mat., to be published.
정용환, 백종혁, 검선재, 김경호, 최병권, 정연호, 한국재료학회지, 8, 368 (1998)

[1] Sabol GP, Kilp GR, Balfour MG, Roberts E, Zirconium in the Nuclear Industry, ASTM STP 1023 (1989) 227.

[2] Yamate K, Oe A, Hayashi M, Okamoto T, Anada H, Hagi S, Amer. Nucl. Soci., 318 (1997)

[3] Mardon JP, Garner G, Beslu P, CharQuet D, Senevat J, Amer. Nucl. Soci, 405 (1997)

[4] 연영명, 정용환, 위명용, 대한금속학회지, 35, 1576 (1997)

[5] 정용환, 한국재료학회지, 6, 585 (1996)

[6] Isobe T, Matsuo Y, ASTM STP, 1132, 346 (1991)

[7] Urbanic VF, Gilbert RW, IAEA Technical CommitteeMeeting on Fundamental Aspects of Corrosion of Zr-base Alloys for Water Reactor Enviroments, Portland, Oregon, 11-15 Sept. (1989)

[8] Godlewski J, ASTM STP, 1245, 663 (1994)

[9] Garzarolli F, Seidel H, Tricot R, Gros JP, ASTM STP, 1132, 395 (1991)

[10] Anada H, Herb BJ, Nomoto K, Hagi S, Graham RA, Kuroda T, ASTM STP, 1295, 74 (1996)

[11] Beie HJ, Mitwalsky A, Garzarolli F, Ruhmann H, Sell HJ, ASTM STP, 1245, 615 (1994)

[12] Jeong YH, Beak JH, Kim SJ, Kim HG, Ruhmann H, J. Nucl. Mat., to be published.

[13] 정용환, 백종혁, 검선재, 김경호, 최병권, 정연호, 한국재료학회지, 8, 368 (1998)