Oxidation of AISI 304L and 348 Stainless Steels in Water at High Temperatures

Avelar, Alan Matias; Giovedi, Claudia; Abe, Alfredo Yuuitiro; Mourão, Marcelo Breda

doi:10.1590/1980-5373-MR-2020-0373

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Article • Mat. Res. 23 (6) • 2020 • https://doi.org/10.1590/1980-5373-MR-2020-0373 copy

Oxidation of AISI 304L and 348 Stainless Steels in Water at High Temperatures

Authorship SCIMAGO INSTITUTIONS RANKINGS

Oxidation of AISI 304L and 348 stainless steels was investigated in water at 1000 – 1350 °C by TGA, SEM, EDS, and Raman spectroscopy. Linear-Parabolic kinetics and multilayer oxide scales with voids were found for both alloys. Based on the experimental results, AISI 304L presented higher oxidation resistance and higher activation energy. Zircaloy-4 kinetic results were used for validation and performance comparison. In severe accidents conditions, stainless steel might lead to a faster hydrogen production comparing to Zircaloy.

Keywords:
Stainless steel; Oxidation; Hydrogen; AISI 348; AISI 304L

Chemical Element	AISI 304L	AISI 348	Zr-4
Fe	71.65	68.63	0.20
Cr	18.50	17.45	0.10
Ni	8.30	10.94	-
C	0.008	0.052	0.01
Si	0.13	0.42	-
Mn	0.90	1.61	-
P	0.008	0.017	-
Cu	0.36	-	-
V	0.02	-	-
Ta	<0.05	<0.005	-
Co	0.05	0.023	-
Nb	<0.01	0.83	-
S	0.0025	0.003	-
B	0.0008	0.0007	-
N	0.0055	0.018	-
O	-	-	0.13
Sn	-	-	1.36
Zr	-	-	98.20

Material /	AISI 348	304L SS	304 SS	304 SS
Kinetic Parameter	This study	Brassfield et al. (1968)⁷7 Massey CP, Terrani KA, Dryepondt SN, Pint BA. Cladding burst behavior of Fe-based al loys under LOCA. J Nucl Mater. 2016;470:128-38. http://dx.doi.org/10.1016/j.jnucmat.2015.12.018. http://dx.doi.org/10.1016/j.jnucmat.2015... ^,¹⁵15 Brassfield HC, White JF, Sjodahl L, Bittel JT. Recommended property and reaction kinetics data for use in evaluating a light-water-cooled reactor loss of coolant incident involving Zircaloy-4 or 304SS Clad UO2, GEMP-482. Cincinnati: General Electric Co.; 1968. (Report No.: GEMP-482).	Ishida et al.⁷7 Massey CP, Terrani KA, Dryepondt SN, Pint BA. Cladding burst behavior of Fe-based al loys under LOCA. J Nucl Mater. 2016;470:128-38. http://dx.doi.org/10.1016/j.jnucmat.2015.12.018. http://dx.doi.org/10.1016/j.jnucmat.2015... ^,¹⁶16 Ishida T, Harayama Y, Yaguchi S. Oxidation of 304 stainless steel in high temperature. J Nucl Mater. 1986;140(1):74-84. http://dx.doi.org/10.1016/0022-3115(86)90198-4. http://dx.doi.org/10.1016/0022-3115(86)9...	Ishida et al.⁷7 Massey CP, Terrani KA, Dryepondt SN, Pint BA. Cladding burst behavior of Fe-based al loys under LOCA. J Nucl Mater. 2016;470:128-38. http://dx.doi.org/10.1016/j.jnucmat.2015.12.018. http://dx.doi.org/10.1016/j.jnucmat.2015... ^,¹⁶16 Ishida T, Harayama Y, Yaguchi S. Oxidation of 304 stainless steel in high temperature. J Nucl Mater. 1986;140(1):74-84. http://dx.doi.org/10.1016/0022-3115(86)90198-4. http://dx.doi.org/10.1016/0022-3115(86)9...
	1000 °C ≤ T ≤ 1350 °C	1000 °C ≤ T ≤ 1375 °C	900 °C ≤ T ≤ 1200 °C	1200 °C < T ≤ 1350 °C
A₀ (kg²/m⁴4 Ganguly C, Roy PR. A comparative study of zircaloy and stainless steel as cladding material for pressurised water reactor. Bombay, India: Bhabha Atomic Research Centre; 1977./s)	4.85 x 10⁷	2.40 x 10⁸	7.34 x 10³	1.85 x 10¹¹
E_A (kJ/mol)	333-354	343-363	240-277	442-498

Material /	Zr-4	Cathcart-Pawel (CP)²¹21 Billone MC, Chung HM, Yan Y. Steam oxidation kinetics of zirconium. Argonne: Argonne National Laboratory; 2002.^,²³23 Cathcart JV, Pawel RE, McKee RA, Druschel RE, Yurek GJ, Campbell JJ, et al. Zirconium metal-water oxidation kinetics, IV: reaction rate studies. Oak Ridge: Oak Ridge National Laboratory; 1977. (Report No.: ORNL/NUREG-17).	Baker-Just (BJ)²⁰20 Baker LJ, Just LC. Studies of metal-water reactions at high temperatures experimental-and theoretical studies of the zirconium-water reaction. AEC Research and Development Report. Argonne: Argonne National Laboratory; 1962. (Report No.: ANL-6548). http://dx.doi.org/10.2172/4781681. http://dx.doi.org/10.2172/4781681...
Kinetic Parameter	This study
A₀ (kg²/m⁴4 Ganguly C, Roy PR. A comparative study of zircaloy and stainless steel as cladding material for pressurised water reactor. Bombay, India: Bhabha Atomic Research Centre; 1977./s)	119	36.22	409.97
E_A (kJ/mol)	176	167	190

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