Performance of FeCrAl for accident-tolerant fuel cladding in high-temperature steam
Source abstract
Abstract
Abstract The very high temperature (≥1400°C) steam oxidation resistance of thin-walled FeCrAl tubes is being investigated as an alternative to Zr-based alloys for enhanced accident-tolerant light water reactor fuel cladding. Initial work examined commercial FeCrAl with ~20% Cr in ramp testing with 1 min hold times at temperatures up to 1700°C. At 1400–1500°C, excellent oxidation resistance was observed with thin external alumina scales formed in contrast to the thick oxides formed on Zircaloy-4 under similar conditions. For an optimized FeCrAl with 13% Cr, one batch of tubing performed poorly at 1400°C, while the second batch formed a protective scale at 1400°C but was fully oxidized at 1500°C. Differences in performance between two test rigs suggest a role of gas velocity, and initial work on bulk alumina specimens has quantified an evaporation rate. However, some results suggest that melting is occurring well below 1500°C. This behavior is still being investigated.
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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.
Affiliations
Oak Ridge National Laboratory , P.O. Box 2008 , Oak Ridge , TN 37831-6156, USA
References (43)
Show source-provided references
1. Cheng T, Keiser JR, Brady MP, Terrani KA, Pint BA. Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure. J Nucl Mater 2012; 427: 396–400.10.1016/j.jnucmat.2012.05.007 ↗
2. Edmondson PD, Briggs SA, Yamamoto Y, Howard RH, Sridharan K, Terrani KA, Field KG. Irradiation-enhanced α′ precipitation in model FeCrAl alloys. Scripta Mater 2016; 116: 112–116.10.1016/j.scriptamat.2016.02.002 ↗
3. Field KG, Gussev MN, Yamamoto Y, Snead LL. Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications. J Nucl Mater 2014; 454: 352–358.10.1016/j.jnucmat.2014.08.013 ↗
4. Field KG, Hu X, Littrell K, Yamamoto Y, Snead LL. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys. J Nucl Mater 2015; 465: 746–755.10.1016/j.jnucmat.2015.06.023 ↗
5. Gauntt R, Kalinich D, Cardoni J, Phillips J, Goldmann A, Pickering S, Francis M, Robb K, Ott L, Wang D, Smith C, St.Germain S, Schwieder D, Phelan C. Fukushima Daiichi accident study (status as of April 2012). Sandia National Laboratory Report, SAND2012-6173, Albuquerque, NM, 2012.10.2172/1055601 ↗
6. Gurrappa I, Weinbruch S, Naumenko D, Quadakkers WJ. Factors governing breakaway oxidation of FeCrAl-based alloys. Mater Corros 2000; 51: 224–235.10.1002/(SICI)1521-4176(200004)51:4<224::AID-MACO224>3.3.CO;2-2 ↗
7. Hu XX, Terrani KA, Wirth BD, Snead LL. Hydrogen permeation in FeCrAl alloys for LWR cladding application. J Nucl Mater 2015; 461: 282–291.10.1016/j.jnucmat.2015.02.040 ↗
8. Jerebtsov DA, Mikhailov GG, Sverdina SV. Phase diagram of the system: Al2O3–ZrO2. Ceram Inter 2000; 26: 821–823.10.1016/S0272-8842(00)00023-7 ↗
9. Jönsson B, Svedberg C. Limiting factors for Fe-Cr-Al and NiCr in controlled industrial atmospheres. Mater Sci Forum 1997; 251–254: 551–558.10.4028/www.scientific.net/MSF.251-254.551 ↗
10. Jönsson B, Berglund R, Magnusson J, Henning P, Hättestrand M. High temperature properties of a new powder metallurgical FeCrAl alloy. Mater Sci Forum 2004; 461–464: 455–462.10.4028/www.scientific.net/MSF.461-464.455 ↗
11. Jönsson B, Lu Q, Chandrasekaran D, Berglund R, Rave F. Oxidation and creep limited lifetime of Kanthal APMT®, a dispersion strengthened FeCrAlMo alloy designed for strength and oxidation resistance at high temperatures. Oxid Met 2013; 79: 29–39.10.1007/s11085-012-9324-4 ↗
12. Katoh Y, Snead LL, Szlufarska I, Weber WJ. Radiation effects in SiC for nuclear structural applications. Curr Opin Solid State Mater Sci 2012; 16: 143–152.10.1016/j.cossms.2012.03.005 ↗
13. Massey CP, Terrani KA, Dryepondt SN, Pint BA. Cladding burst behavior of Fe-based alloys under LOCA. J Nucl Mater 2016; 470: 128–138.10.1016/j.jnucmat.2015.12.018 ↗
14. Naumenko D, Pint BA, Quadakkers WJ. Current thoughts on reactive element effects in alumina-forming systems – in memory of John Stringer. Oxid Met 2016; 86: 1–43.10.1007/s11085-016-9625-0 ↗
15. Opila EJ. Volatility of common protective oxides in high-temperature water vapor: current understanding and unanswered questions. Mater Sci Forum 2004; 461–464: 765–774.10.4028/www.scientific.net/MSF.461-464.765 ↗
16. Opila EJ, Myers DL. Alumina volatility in water vapor at elevated temperatures. J Am Ceram Soc 2004; 87: 1701–1705.10.1111/j.1551-2916.2004.01701.x ↗
17. Ott LJ, Robb KR, Wang D. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions. J Nucl Mater 2014; 448: 520–533.10.1016/j.jnucmat.2013.09.052 ↗
18. Pettit FS, Randklev EH, Felten EJ. Formation of NiAl2O4 by solid state reaction. J Am Ceram Soc 1966; 49: 199–203.10.1111/j.1151-2916.1966.tb13233.x ↗
19. Pint BA. Optimization of reactive element additions to improve oxidation performance of alumina-forming alloys. J Am Ceram Soc 2003; 86: 686–695.10.1111/j.1151-2916.2003.tb03358.x ↗
20. Pint BA, DiStefano JR, Wright IG. Oxidation resistance: one barrier to moving beyond Ni-base superalloys. Mater Sci Eng A 2006a; 415: 255–263.10.1016/j.msea.2005.09.091 ↗
21. Pint BA, Haynes JA, Zhang Y, More KL, Wright IG. The effect of water vapor on the oxidation behavior of Ni-Pt-Al coatings and alloys. Surf Coat Technol 2006b; 201: 3852–3856.10.1016/j.surfcoat.2006.07.244 ↗
22. Pint BA, Dryepondt S, Rouaix-Vande Put A, Zhang Y. Mechanistic- based lifetime predictions for high temperature alloys and coatings. J Oper Manag 2012; 64: 1454–1460.10.1007/s11837-012-0474-2 ↗
23. Pint BA, Terrani KA, Brady MP, Cheng T, Keiser JR. High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. J Nucl Mater 2013; 440: 420–427.10.1016/j.jnucmat.2013.05.047 ↗
24. Pint BA, Dryepondt S, Unocic KA, Hoelzer DT. Development of ODS FeCrAl for compatibility in fusion and fission applications. J Oper Manag 2014; 66: 2458–2466.10.1007/s11837-014-1200-z ↗
25. Pint BA, Terrani KA, Yamamoto Y, Snead LL. Material selection for accident tolerant fuel cladding. Metallurg Mater Trans E 2015a; 2: 190–196.10.1007/s40553-015-0056-7 ↗
26. Pint BA, Unocic KA, Terrani KA. The effect of steam on the high temperature oxidation behavior of alumina-forming alloys. Mater High Temp 2015b; 32: 28–35.10.1179/0960340914Z.00000000058 ↗
27. Quadakkers WJ, Bennett MJ. Oxidation induced lifetime limits of thin walled, iron based, alumina forming, oxide dispersion strengthened alloy components. Mater Sci Technol 1994; 10: 126–131.10.1179/026708394790163807 ↗
28. Rebak RB. Alloy selection for accident tolerant fuel cladding in commercial light water reactors. Metal Mater Trans E 2015; 2: 197–207.10.1007/s40553-015-0057-6 ↗
29. Robb KR, Francis MW, Ott LJ. Insight from Fukushima Daiichi unit 3 investigations using MELCOR. Nucl Technol 2014; 186: 145–160.10.13182/NT13-43 ↗
30. Robb KR, McMurray JW, Terrani KA. Severe accident analysis of BWR core fueled with UO2/FeCrAl with updated materials and melt properties from experiments. ORNL TM-2016/237, Oak Ridge, TN, 2016.10.2172/1259432 ↗
31. Steinbrück M, Boettcher M. Air oxidation of Zircaloy-4, M5(R) and ZIRLO(TM) cladding alloys at high temperatures. J Nucl Mater 2011; 414: 276–285.10.1016/j.jnucmat.2011.04.012 ↗
32. Stott FH, Wood GC, Stringer J. The influence of alloying elements on the development and maintenance of protective scales. Oxid Met 1995; 44: 113–145.10.1007/BF01046725 ↗
33. Terrani KA, Parish CM, Shin D, Pint BA. Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure. J Nucl Mater 2013; 438: 64–71.10.1016/j.jnucmat.2013.03.006 ↗
34. Terrani KA, Zinkle SJ, Snead LL. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding. J Nucl Mater 2014a; 448: 420–435.10.1016/j.jnucmat.2013.06.041 ↗
35. Terrani KA, Pint BA, Parish CM, Silva CM, Snead LL, Katoh Y. Silicon carbide oxidation in steam up to 2 MPa. J Am Ceram Soc 2014b; 97: 2331–2352.10.1111/jace.13094 ↗
36. Terrani KA, Yang Y, Kim YJ, Rebak R, Meyer III HM, Gerczak TJ. Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation. J Nucl Mater 2015; 465: 488–498.10.1016/j.jnucmat.2015.06.019 ↗
37. Terrani KA, Pint BA, Kim YJ, Unocic KA, Yang Y, Silva CM, Meyer HM, Rebak RB. Uniform corrosion of FeCrAl alloys in LWR coolant environments. J Nucl Mater 2016; 479: 36–47.10.1016/j.jnucmat.2016.06.047 ↗
38. Unocic KA, Hoelzer DT, Pint BA. The microstructure and environmental resistance of low-Cr ODS FeCrAl. Mater High Temp 2015; 32: 123–132.10.1179/0960340914Z.00000000088 ↗
39. Unocic KA, Yamamoto Y, Pint BA. Effect of Al and Cr content on air and steam oxidation of FeCrAl alloys and commercial APMT alloy. Oxid Met 2017; 87: 431–441.10.1007/s11085-017-9745-1 ↗
40. Vierow K, Liao Y, Johnson J, Kenton M, Gauntt R. Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes. Nucl Eng Design 2004; 234: 129–145.10.1016/j.nucengdes.2004.09.001 ↗
41. Yamamoto Y, Pint BA, Terrani KA, Field KG, Yang Y, Snead LL. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. J Nucl Mater 2015; 467: 703–716.10.1016/j.jnucmat.2015.10.019 ↗
42. Yan Y, Keiser JR, Terrani KA, Bell GL, Snead LL. Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions. J Nucl Mater 2014; 448: 436–440.10.1016/j.jnucmat.2013.05.071 ↗
43. Zinkle SJ, Terrani KA, Gehin JC, Ott LJ, Snead LL. Accident tolerant fuels for LWRs: a perspective. J Nucl Mater 2014; 448: 374–379.10.1016/j.jnucmat.2013.12.005 ↗