Zr-0.4Sn-1.5Nb-0.2Fe 합금의 인장특성

이명호; 김준환; 최병권; 정용환; M.H. Lee; J.H. Kim; B.K. Choi; Y.H. Jeong

Korean Journal of Materials Research, Vol.14, No.10, 713-718, October, 2004

DOI10.3740/MRSK.2004.14.10.713 Export Citation

Zr-0.4Sn-1.5Nb-0.2Fe 합금의 인장특성

Tensile Properties of Zr-0.4Sn-1.5Nb-0.2Fe

이명호^†, 김준환, 최병권, 정용환

한국원자력연구소 지르코늄신합금핵연료피복관개발팀

M.H. Lee^†, J.H. Kim, B.K. Choi, and Y.H. Jeong

Advanced Zr Alloy Development, KAERI, Daejon, 305-353, Korea

E-mail:

To study the dynamic strain aging behavior of Zr-0.4Sn-1.5Nb-0.2Fe sample tube for nuclear fuel cladding in the range of pressurized water reactor (PWR) operation temperature, the tensile tests of the tube specimens, which had been finally heat-treated at 470 ? Cand510 ? C , had been carried out with the strain rate 1.67×10 ?2 /sand8.33×10 ?5 /s at the various temperatures from room temperature to 500 ? C . It was observed that the elongation of the specimens got shortened as the temperature increased from 200 ? Cto340 ? C . The specimens that were finally heat-treated at 470 ? C showed a plateau more remarkably on the plot of yield strength-temperature than those heat-treated at 510 ? C . In the range of 310∼400 ? C , the strain rate sensitivity of the specimens finally heat-treated at 510 ? C was 30.4%∼33.7% lower but the work hardening exponent index of the specimens was a little higher than that without dynamic strain aging effect.

Keywords:cladding tube;Zr-based alloy;dynamic strain aging

[References]

Lee D, Metallurgical Trans, 1, 1607 (1970)
Ramachandran V, Reed-Hill RE, Metallugical Trans., 1, 2105 (1970)
Park KS, Lee BW, J. KNS., 21(2) (1989)
Yi JK, Park HB, Park GS, Lee BW, J. Nucl. Mater., 189, 353 (1992)
Kim SK, Kim HS, Hong SI, Choi CB, Kim KT, J. Kor. Inst. Met. & Mater., 37(12), 1482 (1999)
Talia JE, Povolo F, J. Nuci. Mater., 67, 198 (1977)
Lee KW, Kim SK, Kim KT, Hong SI, J. Nuci. Mater., 295, 21 (2001)
Garde AM, Aigeltinger E, Woodruff BN, Reed-Hill RE, Metallugical Trans. A, 6A, 1183 (1975)
MOST, Development of Advanced PWR Fuel Technology, KAERI/RR-2335/2002 (2003) (2003)
Garde AM, Chung HM, Kassner TF, ANL-77-30 (1977) (1977)
KAERI, Specification for the manufacturing of the TREX (Tube Reduced Extrusion) for KAERI Cladding Tubes Revision 1 (2001) (2001)
KAERI, Specification for the manufacturing of the KAERI cladding tubes (2000) (2000)
B.G, Vignoul G, Fabrication Report MERD 7408, WahChang, Nov. (2001) (2001)
Akhtar A, Acta Metallurgica, 21, 1 (1973)
Hammad AM, El-Mashri SM, Nasr MA, J. Nucl. Mater., 186, 166 (1992)
Hertzberg RW, Deformation and Fracture Mecha-nics of Engineering Materials, 2nd ed., p. 18, John Wiley & Sons, New York, (1983) (1983)

[Referenced By]

[Related Articles]

[1] Lee D, Metallurgical Trans, 1, 1607 (1970)

[2] Ramachandran V, Reed-Hill RE, Metallugical Trans., 1, 2105 (1970)

[3] Park KS, Lee BW, J. KNS., 21(2) (1989)

[4] Yi JK, Park HB, Park GS, Lee BW, J. Nucl. Mater., 189, 353 (1992)

[5] Kim SK, Kim HS, Hong SI, Choi CB, Kim KT, J. Kor. Inst. Met. & Mater., 37(12), 1482 (1999)

[6] Talia JE, Povolo F, J. Nuci. Mater., 67, 198 (1977)

[7] Lee KW, Kim SK, Kim KT, Hong SI, J. Nuci. Mater., 295, 21 (2001)

[8] Garde AM, Aigeltinger E, Woodruff BN, Reed-Hill RE, Metallugical Trans. A, 6A, 1183 (1975)

[9] MOST, Development of Advanced PWR Fuel Technology, KAERI/RR-2335/2002 (2003) (2003)

[10] Garde AM, Chung HM, Kassner TF, ANL-77-30 (1977) (1977)

[11] KAERI, Specification for the manufacturing of the TREX (Tube Reduced Extrusion) for KAERI Cladding Tubes Revision 1 (2001) (2001)

[12] KAERI, Specification for the manufacturing of the KAERI cladding tubes (2000) (2000)

[13] B.G, Vignoul G, Fabrication Report MERD 7408, WahChang, Nov. (2001) (2001)

[14] Akhtar A, Acta Metallurgica, 21, 1 (1973)

[15] Hammad AM, El-Mashri SM, Nasr MA, J. Nucl. Mater., 186, 166 (1992)

[16] Hertzberg RW, Deformation and Fracture Mecha-nics of Engineering Materials, 2nd ed., p. 18, John Wiley & Sons, New York, (1983) (1983)