TY - GEN
T1 - Oxidation kinetics of austenitic stainless steels as SCWR fuel cladding candidate materials in supercritical water
AU - Abe, Hiroshi
AU - Suzuki, Ryuichi
AU - Watanabe, Yutaka
N1 - Funding Information:
Present study includes the result of “Research and Development of the Super Fast Reactor” entrusted to The University of Waseda by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).
Publisher Copyright:
© The Minerals, Metals & Materials Society 2018.
PY - 2018
Y1 - 2018
N2 - The oxidation kinetics of supercritical-water-cooled reactor (SCWR) fuel cladding candidate materials, e.g. 15Cr-20Ni stainless steel (1520 SS) in supercritical water at 650 and 700, °C under 24, MPa has been investigated. Characteristics of oxide layers and its relation to oxidation behaviors are also studied. The applicability of the candidate materials for the fuel cladding of SCWR from oxidation kinetics, spalling susceptibility of oxide layer, and breakdown of Cr2O3 layer points of view has been discussed. The results indicate that the threshold condition for spalling of oxide layer is different at 650 and 700, °C. The decrease in oxidation kinetics of 1520 SS with time correspond to the change in rate-limiting process of oxidation from mass transfer through an Fe oxides to mass transfer through a Cr rich oxide layer with time. Based on the oxidation kinetics obtained in this study, 1520 SS is considered suitable for a fuel cladding of SCWR in combination with appropriate CW process. However, detailed evaluation and countermeasures for the degradation due to nodular oxidation are needed before application of tube-shaped 1520 SS in supercritical water at 700, °C. On the other hand, it is estimated that the use of that at 650, °C is acceptable because the weight gain after long-term exposure was considered to be much less than the threshold condition of the spalling.
AB - The oxidation kinetics of supercritical-water-cooled reactor (SCWR) fuel cladding candidate materials, e.g. 15Cr-20Ni stainless steel (1520 SS) in supercritical water at 650 and 700, °C under 24, MPa has been investigated. Characteristics of oxide layers and its relation to oxidation behaviors are also studied. The applicability of the candidate materials for the fuel cladding of SCWR from oxidation kinetics, spalling susceptibility of oxide layer, and breakdown of Cr2O3 layer points of view has been discussed. The results indicate that the threshold condition for spalling of oxide layer is different at 650 and 700, °C. The decrease in oxidation kinetics of 1520 SS with time correspond to the change in rate-limiting process of oxidation from mass transfer through an Fe oxides to mass transfer through a Cr rich oxide layer with time. Based on the oxidation kinetics obtained in this study, 1520 SS is considered suitable for a fuel cladding of SCWR in combination with appropriate CW process. However, detailed evaluation and countermeasures for the degradation due to nodular oxidation are needed before application of tube-shaped 1520 SS in supercritical water at 700, °C. On the other hand, it is estimated that the use of that at 650, °C is acceptable because the weight gain after long-term exposure was considered to be much less than the threshold condition of the spalling.
KW - Austenitic stainless steel
KW - Cold working
KW - Fuel cladding material
KW - Oxidation kinetics
KW - Super critical water reactor
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U2 - 10.1007/978-3-319-67244-1_75
DO - 10.1007/978-3-319-67244-1_75
M3 - Conference contribution
AN - SCOPUS:85042509111
SN - 9783319672434
T3 - Minerals, Metals and Materials Series
SP - 1181
EP - 1194
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Paraventi, Denise
A2 - Wright, Michael
A2 - Jackson, John H.
PB - Springer International Publishing
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Y2 - 13 August 2017 through 17 August 2017
ER -