High-pressure hydriding of Zircaloy cladding by the thermogravimetry and tube-burst techniques
Source abstract
Abstract
Abstract Hydriding kinetics of modified Zircaloy claddings was studied by the thermogravimetric method at 400 °C and the tube-burst technique at 315 °C. Some specimens were prefilmed with a thin oxide layer by air oxidation on both the inner and outer surfaces which were either pickled or blasted. In the thermogravimetric test, the hydriding rates of bare cladding specimens (no oxide prefilm) were in the range 0.9–1.6 mg/cm2 h with little effect of the surface treatment. Incubation times were less than 1 h or even zero. In the tube-burst test, immediate and extensive hydrogen uptake was observed for these non-coated specimens. On the other hand, the cladding specimens with oxide prefilm exhibited lower hydriding rates ranging from 0.01 to 0.05 mg/cm2 h and incubation times increased to 42 h. In addition, no hydrogen uptake was observed for all oxide-coated specimens for 100–750 h.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Hydrogen Storage and Materials · Industrial Gas Emission Control
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References (17)
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1. Li · Rad. Phys. Chem. · 1999 · 54 · 30110.1016/S0969-806X(98)00228-X ↗
2. J.C. Clayton, in: Proc. Eighth International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1023, 1989. p. 26610.1520/STP18870S ↗
3. D.R. Olander, S. Vaknin, Secondary hydriding of defected Zircaloy-clad fuel rods, Report EPRI TR-101773, 1993
4. R.L. Yang, O. Oze, S.K. Yagnik, B. Cheng, H.H. Klepfer, N. Kjaer-Pedersen, et al. EPRI failed fuel degradation R&D program. In: Proceedings of the International Topical Meeting on LWR Fuel Performance, West Palm Beach, FL, USA, American Nuclear Society, 1994
5. Kim · High Temp.–High Press. · 1995 · 27&28 · 55510.1068/htrt104 ↗
6. Kim · J. Nucl. Mater. · 1997 · 246 · 4310.1016/S0022-3115(97)00066-4 ↗
7. Olander · J. Nucl. Mater. · 1997 · 248 · 21410.1016/S0022-3115(97)00172-4 ↗
8. Kim · J. Nucl. Mater. · 1996 · 240 · 2710.1016/S0022-3115(96)00478-3 ↗
9. Kim · J. Nucl. Mater. · 1997 · 245 · 15210.1016/S0022-3115(97)00018-4 ↗
10. Marshall · J. Less-Common Met. · 1967 · 13 · 4510.1016/0022-5088(67)90045-8 ↗
11. S. Aronson, Some experiments on the permeation of hydrogen through oxide films on Zirconium, Report WAPD-BT-19, 1960
12. Une · J. Less-Common Met. · 1978 · 57 · 9310.1016/0022-5088(78)90165-0 ↗
13. H.S. Hong, W.E. Wang, D.R. Olander, High pressure hydriding of Zircaloy cladding by the tube-burst technique. In: International Topical Meeting on LWR Fuel Performance, Park City, UT, American Nuclear Society, 2000
14. Hong · J. Nucl. Mater. · 2001 · 297 · 10710.1016/S0022-3115(01)00616-X ↗
15. Shannon · Corrosion · 1963 · 19 · 41410.5006/0010-9312-19.12.414 ↗
16. R.L. Gibby, Hydriding of PRTR fuel rod end caps, Report BNWL 150, 1965
17. R.F. Boyle, T.J. Kisiel, Hydrogen permeation of Zircaloy-2 corrosion films, Report WAPD-BT-10, 1958