journal article·2014-05

Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction

M.T. Farmer, L. Leibowitz, K.A. Terrani, K.R. Robb

Journal of Nuclear Materials· Volume 448· Issue 1-3
Publisher page

Abstract

Abstract Simple scoping models that can be used to evaluate ATF performance under severe accident conditions have been developed. The methodology provides a fundamental technical basis (a.k.a. metric) based on the thermodynamic boundary for evaluating performance relative to that of traditional Zr-based claddings. The initial focus in this study was on UO 2 fuel with the advanced claddings 310 SS, D9, FeCrAl, and SiC. The evaluation considered only energy release with concurrent combustible gas production from fuel–cladding–coolant interactions and, separately, molten core–concrete interactions at high temperatures. Other important phenomenological effects that can influence the rate and extent of cladding decomposition (e.g., eutectic interactions, degradation of other core constituents) were not addressed. For the cladding types addressed, potential combustible gas production under both in-vessel and ex-vessel conditions was similar to that for Zr. However, exothermic energy release from cladding oxidation was substantially less for iron-based alloys (by at least a factor of 4), and modestly less (by ∼20%) for SiC. Data on SiC-clad UO 2 fuel performance under severe accident conditions are sparse in the literature; thus, assumptions on the nature of the cladding decomposition process were made in order to perform this initial screening evaluation. Experimental data for this system under severe accident conditions is needed for a proper evaluation and comparison to iron-based claddings.
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Research context

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

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References (21)

Show source-provided references
1. Pint · J. Nucl. Mater. · 2013 · 440 · 42010.1016/j.jnucmat.2013.05.047 ↗
2. Cheng · J. Nucl. Mater. · 2012 · 427 · 39610.1016/j.jnucmat.2012.05.007 ↗
3. Ott · J. Nucl. Mater. · 2014 · 448 · 52010.1016/j.jnucmat.2013.09.052 ↗
4. Hofmann · J. Nucl. Mater. · 1999 · 270 · 19410.1016/S0022-3115(98)00899-X ↗
5. Steinbrück · Nucl. Eng. Des. · 2010 · 240 · 171410.1016/j.nucengdes.2010.03.021 ↗
6. J.V. Cathcart, R.E. Pawel, R.A. McKee, R.E. Druschel, G.J. Yurek, J.J. Campbell, et al., Zirconium Metal–Water Oxidation Kinetics, IV: Reaction Rate Studies, ORNL/NUREG-17, Oak Ridge National Laboratory, 1977.10.2172/7317596 ↗
7. Steinbrück · Oxid. Met. · 2011 · 76 · 21510.1007/s11085-011-9249-3 ↗
8. R. Gauntt, D. Kalinich, J. Cardoni, J. Phillips, A. Goldmann, S. Pickering, et al., Fukushima Daiichi Accident Study (Status as of April 2012), SAND2012-6173, Sandia National Laboratories, 2012.10.2172/1055601 ↗
9. Terrani · J. Nucl. Mater. · 2012 · 427 · 20910.1016/j.jnucmat.2012.05.021 ↗
10. Olander · Eng. Des. · 1994 · 148 · 253
11. Terrani · J. Nucl. Mater. · 2014 · 448 · 42010.1016/j.jnucmat.2013.06.041 ↗
12. Ellingham · J. Soc. Chem. Ind. · 1944 · 63 · 12510.1002/jctb.5000630501 ↗
13. T. Alpettaz, S. Gossé, J. Braun, C. Sauder, S. Chatain, P. Allegri, et al., Investigation of the high temperature chemical interaction between UO2 fuel and Fe, B4C and SiC using Knudsen cell mass spectrometry, Presented at Nucl. Mater 2012, Osaka, Japan, 2012.
14. C. M. Silva, S. L. Voit, Y. Katoh, Evaluation of CVD and CVC SiC Reactivity towards UO2, Oak Ridge National Laboratory, Unpublished 2013.
15. The Chemical thermodynamics of actinide elements and compounds Part 6. The actinide carbides
16. Opila · J. Am. Ceram. Soc. · 1997 · 80 · 19710.1111/j.1151-2916.1997.tb02810.x ↗
17. Opila · J. Am. Ceram. Soc. · 1999 · 82 · 62510.1111/j.1151-2916.1999.tb01810.x ↗
18. More · J. Am. Ceram. Soc. · 2000 · 83 · 21110.1111/j.1151-2916.2000.tb01172.x ↗
19. K.A. Terrani et al., SiC Oxidation in Steam, J. Am. Ceramic Soc. (2013) (submitted for publication).
20. Fink · J. High Temp. Mater. Sci. · 1995 · 33 · 51
21. M. Sherman et al., The behavior of hydrogen during accidents in LWRs, NUREG/CR-1561, US Nuclear Regulatory Commission, 1980.