journal article·2000-08

Crack growth pattern and threshold stress intensity factor, KIH, of Zr–2.5Nb alloy with the notch direction

Young Suk Kim, Sang Chul Kwon, Sung Soo Kim

Journal of Nuclear Materials· Volume 280· Issue 3
Publisher page

Abstract

Abstract The objective of this study is to obtain a better understanding of the threshold stress intensity factor for an initiation of delayed hydride cracking (DHC) in a Zr–2.5Nb pressure tube. By changing the crack propagation from the longitudinal direction to the circumferential direction, the threshold stress intensity factor, KIH, and the crack growth pattern were investigated in the Zr–2.5Nb pressure tube with a strong circumferential texture. The threshold stress intensity factor, KIH, was discussed phenomenologically based on the crack growth pattern and analytically as a function of the tilting angle of hydride habit planes to the cracking plane. A supplementary experiment was conducted to demonstrate a linear decrease of KIH with an increase in the basal pole component in the cracking plane. Thus, it is concluded that the DHC is controlled by the nucleation and growth of the hydride precipitates on the habit plane.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (18)

Show source-provided references
1. K.S. Choi, Development of regulatory guideline for the pressure tube integrity of domestic CANDU reactors, Korea Institute of Nuclear Safety Report KINS/AR-122, 1991
2. B.A. Cheadle, E.G. Price, Operating performance of CANDU pressure tubes, Atomic Energy of Canada Limited Report AECL-9939, 1989
3. C.E. Coleman, J.F.R. Ambler, Zirconium in the Nuclear Industry, ASTM STP 633, American Society for Testing and Materials, 1977, p. 58910.1520/STP35593S ↗
4. Nuttall · J. Nucl. Mater. · 1979 · 80 · 27910.1016/0022-3115(79)90191-0 ↗
5. B.A. Cheadle, C.E. Coleman, J.F.R. Ambler, in: Proceedings of the Sixth International Symposium on Zirconium in the Nuclear Industry, ASTM STP 939, 1987, p. 22410.1520/STP28122S ↗
6. Westlake · J. Nucl. Mater. · 1968 · 26 · 20810.1016/0022-3115(68)90072-X ↗
7. Young Suk Kim et al., Development of Zr–Nb alloys for pressure tubes, Korea Atomic Energy Research Institute Report KAERI/RR-1523/94, 1995
8. J.Y. Oh, MS thesis, Korea Advanced Institute of Science and Technology, 1995
9. S. Sagat, C.E. Coleman, M. Griffiths, B.J.S. Wilkins, in: Proceedings of the 10th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1245, 1994, p. 3510.1520/STP15183S ↗
10. Perovic · Acta Metall. · 1983 · 31 · 138110.1016/0001-6160(83)90008-1 ↗
11. C.E. Coleman, in: Proceedings of the Fifth Conference on Zirconinum in the Nuclear Industry, ASTM STP 754, 1982, p. 393
12. Huang · Metall. Trans. · 1991 · 22A · 204910.1007/BF02669872 ↗
13. Kim · J. Korean Inst. Met. Mater. · 2000 · 38 · 35
14. Shi · J. Nucl. Mater. · 1994 · 208 · 23210.1016/0022-3115(94)90332-8 ↗
15. Anderson · 1995
16. Kim · J. Nucl. Mater. · 1999 · 273 · 5210.1016/S0022-3115(99)00017-3 ↗
17. C.E. Coleman, S. Sagat, K.F. Amouzouvi, Control of microstructure to increase the tolerance of zirconium alloys to hydride cracking, Atomic Energy of Canada Limited Report AECL-9524, 198710.1016/B978-0-08-035764-5.50028-6 ↗
18. Mills · Eng. Frac. Mech. · 1991 · 39 · 24110.1016/0013-7944(91)90040-8 ↗