journal article·2018-11Open access

Influence of kinetic effects on terminal solid solubility of hydrogen in zirconium alloys

Peter Kaufholz, Maik Stuke, Felix Boldt, Marc Péridis

Abstract

The integrity of irradiated zirconium based nuclear fuel cladding is related to the precipitation of hydrides which is closely connected with the solubility of hydrogen. A review on the development of measurement technologies is given and the resulting terminal solid solubilities are reflected with respect to the established model of hydrogen solubility in zirconium alloys. The results often allow for a different interpretation than the established model. An alternative qualitative approach is proposed in which the fixed TSSp for the precipitation of zirconium hydrides is replaced by a kinetic model based on thermal history, total hydrogen content and the cooling rate. The influence of the modification of the model from a fixed TSSp to a kinetically limited TSSd is discussed with respect to the understanding of hydride embrittlement processes in long term storage.
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 (24)

Show source-provided references
1. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
2. Zr-alloys, the nuclear material for water reactor fuel
3. Zirconium alloy corrosion and hydrogen pickup
4. A new cladding embrittlement criterion derived from ring compression tests10.1016/j.nucengdes.2014.03.047 ↗
5. International Atomic Energy Agency · 2010
6. Hydrogen supercharging in zircaloy10.1016/0025-5416(71)90016-4 ↗
7. The role of chemical free energy and elastic strain in the nucleation of zirconium hydride10.1016/j.jnucmat.2013.06.013 ↗
8. Puls · 2012
9. Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, zircaloy-2 and zircaloy-410.1016/0022-3115(67)90047-5 ↗
10. Hydrogen solubility in zirconium alloys determined by thermal diffusion10.1016/0022-3115(67)90048-7 ↗
11. The diffusion and solubility of hydrogen in the alpha phase of zircaloy-210.1016/0022-3115(60)90025-8 ↗
12. The terminal solubility of hydrogen in zirconium alloys between 30 and 400 c
13. Study on the effects of matrix yield strength on hydride phase stability in Zircaloy-2 and Zr2.5 wt% Nb10.1016/j.jnucmat.2011.10.051 ↗
14. Solubility of hydrogen in zircaloy-4: irradiation induced increase and thermal recovery10.1016/S0022-3115(02)00883-8 ↗
15. The terminal solid solubility of hydrogen in zirconium alloys
16. Dissolution and precipitation behaviors of hydries in n18, zry-4 and m5 alloys10.1016/j.ijhydene.2009.07.018 ↗
17. In situ synchrotron x-ray diffraction study of hydrides in zircaloy-4 during thermomechanical cycling10.1016/j.jnucmat.2017.02.027 ↗
18. Zirconium hydride precipitation kinetics in zircaloy-4 observed with synchrotron x-ray diffraction10.1016/j.jnucmat.2015.04.025 ↗
19. Identification and quantification of hydride phases in zircaloy-4 cladding using synchrotron x-ray diffraction10.1016/j.jnucmat.2009.04.004 ↗
20. In situ study of hydride precipitation kinetics and re-orientation in zircaloy using synchrotron radiation10.1016/j.actamat.2010.07.018 ↗
21. Mechanisms of hydride reorientation in zircaloy-4 studied in situ
22. The terminal solid solubility of hydrogen and deuterium in zr-2.5nb alloys10.1016/S0022-3115(95)00217-0 ↗
23. Kinetics of the isothermal decomposition of zirconium hydride: terminal solid solubility for precipitation and dissolution10.1016/j.jnucmat.2018.03.007 ↗
24. Experimental determination of zirconium hydride precipitation and dissolution in zirconium alloy10.1016/j.jnucmat.2018.06.038 ↗