Delayed Hydride Cracking Velocity of Irradiated Zr-2.5Nb Tubes after a 30-Year Operation in the Wolsong Unit 1

Abstract:

Article Preview

The aim of this study is to investigate a change in delayed hydride cracking (DHC) velocity of Zr-2.5Nb tubes with fast neutron fluence (E>1MeV) and predict the DHC velocity of the irradiated Wolsong 1 Zr-2.5Nb tubes at a neutron fluence corresponding to the 30 year design lifetime. To this end, the DHC velocity were determined at temperatures ranging from 100 to 280 oC on unirradiated Zr-2.5Nb tubes and the irradiated Zr-2.5Nb tubes in the Wolsong Unit-1 to the neutron fluence of 8.9x1025 n/m2 (E>1MeV). DHC tests were conducted on the compact tension specimens charged with 34 to 100 ppm hydrogen in accordance with the KAERI DHC procedures that have been validated through a round robin test on DHC velocity of Zr-2.5Nb tubes as an IAEA coordinated research project. Irradiated Zr-2.5Nb tubes had 3 to 5 times higher DHC velocity than that of unirradiated Zr-2.5Nb tubes while the inlet region of the irradiated Zr-2.5Nb tube with the highest yield strength had a slightly higher DHC velocity compared to that of the outlet region with the lowest yield strength. From a normalized correlation of yield strength and DHC velocity of the Zr-2.5Nb tubes, the yield strength was found to govern the DHC velocity of the Zr-2.5Nb tubes irrespective of the neutron fluence and operating temperatures. The DHC velocity of the irradiated Zr-2.5Nb tubes is predicted after a 30 year operation in the Wolsong Unit 1 on the basis of an increase in the yield strength with neutron fluence and a DHC velocity dependence on the yield strength of Zr-2.5Nb tubes.

Info:

Periodical:

Materials Science Forum (Volumes 475-479)

Main Theme:

Edited by:

Z.Y. Zhong, H. Saka, T.H. Kim, E.A. Holm, Y.F. Han and X.S. Xie

Pages:

1409-1414

Citation:

Y. S. Kim et al., "Delayed Hydride Cracking Velocity of Irradiated Zr-2.5Nb Tubes after a 30-Year Operation in the Wolsong Unit 1", Materials Science Forum, Vols. 475-479, pp. 1409-1414, 2005

Online since:

January 2005

Export:

Price:

$38.00

[1] S. Sagat, C.E. Coleman, M. Griffiths and B.J.S. Wilkins: Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245 (ASTM, USA 1994), pp.35-61.

[2] S.B. Ahn, Y.S. Kim and J.K. Kim, KSME, Vol. 26 (2002) p.188.

[3] Y.S. Kim, S.S. Kim and Y.M. Cheong, Journal of Metals, Vol. 55 (2) (2003) p.383.

[4] Y.S. Kim et al.: A manual for Characterization Tests for Zr-2. 5Nb Pressure Tubes, KAERI Technical Report, KAERI/TR-1329/99 (KAERI, 1999).

[5] R.R. Hosbons, P.H. Davies, M. Griffiths, S. Sagat and C.E. Coleman: Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354 (ASTM, USA 2000), pp.122-138.

DOI: https://doi.org/10.1520/stp14298s

[6] M. Griffiths, P.H. Davies, W.G. Davies and S. Sagat: Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP 1423, (ASTM, USA 2002) pp.507-523.

[7] J.Y. Oh, I.S. Kim and Y.S. Kim, J. Nucl. Sci. & Tech., Vol. 37 (2000) p.595.

[8] Y.S. Kim et al.: Proceedings of the KNS Spring Meeting, Kyungju, Korea, (2004).

[9] Y.S. Kim, et al., Metals and Materials Int. Vol. 8 (2002) p.241.

[10] R.R. Hosbons, P.H. Davies, M. Griffiths, S. Sagat and C.E. Coleman: Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, (ASTM, USA 2000) pp.122-138.

DOI: https://doi.org/10.1520/stp14298s

[11] Korea Electric Power Company: Final Safety Analysis Report of the Wolsong Unit-1 Nuclear Power Plant, Chapter 5 (1982).

Fetching data from Crossref.
This may take some time to load.