Related references
Note: Only part of the references are listed.Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions
S. B. Bell et al.
JOURNAL OF NUCLEAR MATERIALS (2021)
High-temperature steam oxidation behavior of alumina-forming duplex FeNiCrAl and ferritic FeCrAl alloys at 800 °C to 1050 °C
Chaewon Kim et al.
CORROSION SCIENCE (2021)
High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
Jean-Christophe Brachet et al.
CORROSION SCIENCE (2020)
Burst behavior of nuclear grade FeCrAI and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions
K. A. Kane et al.
JOURNAL OF NUCLEAR MATERIALS (2020)
A study of the oxidation behaviour of FeCrAl-ODS in air and steam environments up to 1400 °C
K. Lipkina et al.
JOURNAL OF NUCLEAR MATERIALS (2020)
Intermediate temperature corrosion behaviour of Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy (C26M) at 300-600 °C
Nan Li et al.
CORROSION SCIENCE (2019)
Effects of zirconium and oxygen on the oxidation of FeCrAl-ODS alloys under air and steam conditions up to 1500 °C
T. Maeda et al.
JOURNAL OF NUCLEAR MATERIALS (2019)
Oxidation Characteristics of Two FeCrAl Alloys in Air and Steam from 800A°C to 1300A°C
Raul B. Rebak et al.
JOM (2018)
Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors
Hyunmyung Kim et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding
Sebastien Dryepondt et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
Accident tolerant fuel cladding development: Promise, status, and challenges
Kurt A. Terrani
JOURNAL OF NUCLEAR MATERIALS (2018)
Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam
Chongchong Tang et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels
J. W. McMurray et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin wall tube fabrication
Zhiciian Sun et al.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2017)
Current status of materials development of nuclear fuel cladding tubes for light water reactors
Zhengang Duan et al.
NUCLEAR ENGINEERING AND DESIGN (2017)
Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy
Kinga A. Unocic et al.
OXIDATION OF METALS (2017)
First-principles analysis of solute diffusion in dilute bcc Fe-X alloys
C. D. Versteylen et al.
PHYSICAL REVIEW B (2017)
Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
Chongchong Tang et al.
CORROSION REVIEWS (2017)
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
Y. Yamamoto et al.
JOURNAL OF NUCLEAR MATERIALS (2015)
High temperature oxidation of molybdenum in water vapor environments
A. T. Nelson et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments
B. A. Pint et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600-1200 °C
Martin Steinbrueck et al.
OXIDATION OF METALS (2011)
Effect of Fe-Al substrate mechanical properties on alumina scale morphology
S. Dryepondt et al.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2008)
On the Competitive Growth of Alpha and Transient Aluminas During the First Stages of Thermal Oxidation of FeCrAl Alloys at Intermediate Temperatures
Redouane Chegroune et al.
OXIDATION OF METALS (2008)
Oxidation of FeCrAl alloys at 500-900 °C in dry O2
H Josefsson et al.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION (2005)
High temperature oxidation behavior of ODS steels
T Kaito et al.
JOURNAL OF NUCLEAR MATERIALS (2004)
Share Paper
