Optimization of stress relief heat treatment of PHWR pressure tubes (Zr–2.5Nb alloy)
Source abstract
Abstract
Abstract The micro-structure of cold worked Zr–2.5%Nb pressure tube material consists of elongated grains of α-zirconium enclosed by a thin film of β-zirconium phase. This β-Zr phase is unstable and on heating, progressively decomposes to α-Zr phase and β-phase enriched with Nb and ultimately form βNb. Meta-stable ω-phase precipitates as an intermediate step during decomposition depending on the heat treatment schedule, β Zr → α + β enr → α + ω + β enr → α + β enr → α + β Nb Morphological changes occur in the β-zirconium phase during the decomposition. The continuous ligaments of βZr phase turn into a discontinuous array of particles followed by globulization of the β-phase. The morphological changes impose a significant effect on the creep rate and on the delayed hydride cracking velocity due to reduction in the hydrogen diffusion coefficient in αZr. If the continuity of β-phase is disrupted by heat treatment, the effective diffusion coefficient decreases with a concomitant reduction in DHC velocity. The pressure tubes for the Indian PHWRs are made by a process of hot extrusion followed by cold pilgering in two stages and an intermediate annealing. Autoclaving at 400 °C for 36 h ensures stress relieving of the finished tubes. In the present studies, autoclaving duration at 400 °C was varied from 24 h to 96 h at 12 h-steps and the micro-structural changes in the β-phase were observed by TEM. Dislocation density, hardness and the micro-structural features such as thickness of β-phase, inter-particle spacing and volume fraction of the phases were measured at each stage. Autoclaving for a longer duration was found to change the morphology of β-phase and increase the inter-particle spacing. Progressive changes in the aspect ratio of the β-phase and their size and distribution are documented and reported. These micro-structural modifications are expected to decrease DHC velocity during reactor operation.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (10)
Show source-provided references
1. J.W. Evans, P.A. Ross-Ross, J.E. Lesurf, H.E. Thexton, Atomic Energy Canada Limited, Report No. AECL-2982, 1971.
2. D. Warr, V. Perovic, Y.P. Lin, A.C. Wallace, in: Zirconium in Nuclear Industry – 13th International Symposium, 2002, p. 313.10.1520/STP11395S ↗
3. Northwood · Metallography · 1980 · 13 · 9710.1016/0026-0800(80)90009-9 ↗
4. Glen M. Mc Dougall, Vincent F. Urbani, in: Zirconium in Nuclear Industry – 13th International Symposium, 2002, p. 247.
5. Jovanovic · J. Nucl. Mater. · 1997 · 244 · 14110.1016/S0022-3115(96)00732-5 ↗
6. V.F. Urbanic, M. Griffiths, in: Zirconium in Nuclear Industry – 12th International Symposium, ASTM STP 1354, 2000, p. 641.10.1520/STP14321S ↗
7. P. Pande, M. Narayana Rao, D.K. Wali, N. Saibaba, in: Conference Proceedings of “ZARC-91”, Conducted by BARC during 12–13 December 1991, Mumbai, p. 155.
8. Stefan Sagat, Christopher E. Coleman, Malcom Griffiths, Brian J.S. Wilkins, in: Zirconium in Nuclear Industry – 10th International Symposium, 1994, p. 35.10.1520/STP15183S ↗
9. Jovanovic · Mater. Charact. · 1998 · 40 · 1510.1016/S1044-5803(97)00091-0 ↗
10. Jovanovic · Mater. Character. · 2001 · 47 · 25910.1016/S1044-5803(01)00179-6 ↗