journal article·2013-09

The relationship between the amount of oxidation and activation energy on the steam oxidation reaction of Zircaloy-4 cladding

Masaki Amaya, Fumihisa Nagase

Journal of Nuclear Materials· Volume 440· Issue 1-3
Publisher page

Abstract

Abstract Zirconium-based alloys are widely used as cladding material for light-water reactors, and in the case of a loss-of-coolant accident (LOCA), oxidation of the cladding by high temperature steam plays important roles in fuel rod failure and hydrogen generation during the accident. In this study, considering that the oxidation rate is related to the activation energy of the oxidation reaction, the relationship between the amount of oxidation and the activation energy of cladding oxidation by steam was investigated by thermogravimetry. The oxidation rate of the specimen decreased with increasing heating rate. The activation energy of oxidation was evaluated based on a non-isothermal kinetics theory. It was found that the activation energy of oxidation depends on the specimen weight gain. The activation energies showed constant values of ∼300 and ∼180 kJ/mol in the oxidation range between 30 and 120 g/m 2 and above 120 g/m 2 , respectively. A master curve which expresses the amount of steam oxidation of Zircaloy-4 cladding was formulated based on the activation energies obtained.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Thermal and Kinetic Analysis · Thermodynamic and Structural Properties of Metals and Alloys

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

References (16)

Show source-provided references
1. J.V. Cathcart, R.E. Pawel, R.A. Mckee, R.E. Druschel, G. J. Yurek, J.J. Campbell, ORNL/NUREG-17, 1977.
2. Uetsuka · J. Nucl. Mater. · 1989 · 168 · 4710.1016/0022-3115(89)90563-1 ↗
3. Ballinger · J. Nucl. Mater. · 1976 · 62 · 21310.1016/0022-3115(76)90017-9 ↗
4. Kawasaki · J. Nucl. Sci. Technol. · 1978 · 15 · 58910.1080/18811248.1978.9735555 ↗
5. S. Leistikow, G. Schanz, H.V. Berg, KfK, Report 2587, 1978.
6. L. Baker, L.C. Just, ANL-6548, 1962.
7. J.T. Prater, E.L. Courtright, NUREG/CR-4476, 1986.
8. Urbanic · J. Nucl. Mater. · 1978 · 75 · 25110.1016/0022-3115(78)90006-5 ↗
9. Leistikow · Werkst. Korros. · 1985 · 36 · 10510.1002/maco.19850360302 ↗
10. 1990
11. The Japan Society of Mechanical Engineers, JSME Steam Tables, fifth ed., November, 1999.
12. Uetsuka · J. Nucl. Sci. Technol. · 1989 · 26 · 24010.1080/18811248.1989.9734298 ↗
13. Ozawa · J. Thermal Anal. · 1986 · 31 · 54710.1007/BF01914230 ↗
14. Friedman · J. Polym. Sci. · 1964 · C6 · 183
15. Ozawa · Netsu Sokutei · 2004 · 31 · 125
16. Grosse · Adv. Eng. Mater. · 2009 · 11 · 48310.1002/adem.200800344 ↗