Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

KG Field, SA Briggs, K Sridharan, RH Howard… - Journal of Nuclear …, 2017 - Elsevier
The development and understanding of the mechanical properties of neutron-irradiated
FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature …

Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1)

KG Field, MA Snead, Y Yamamoto, KA Terrani - 2018 - osti.gov
FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power
applications including accident tolerant fuel cladding, structural components for fast fission …

The characteristics of serration in Al0. 5CoCrFeNi high entropy alloy

S Niu, H Kou, Y Zhang, J Wang, J Li - Materials Science and Engineering: A, 2017 - Elsevier
Abstract Serrated flow in Al 0.5 CoCrFeNi high entropy alloy (HEA) was studied at the
temperature range of 200–500° C with strain rates from 10− 3 s− 1 to 10− 4 s− 1. Results …

Dynamic strain aging behavior of accident tolerance fuel cladding FeCrAl-based alloy for advanced nuclear energy

Y Zhang, H Wang, X An, G Chen, H Sun… - Journal of Materials …, 2021 - Springer
Abstract The Fe-13Cr-4Al alloy has become a promising candidate material for accident
tolerance fuel (ATF) cladding of light-water reactors (LWRs) due to its excellent oxidation …

Role of loading direction on high-temperature tensile behavior of Fe-13Cr-4Al-2Mo-0.65 Nb alloy

M Chai, Z Han, W Hou, P Liu, Y Song - Materials Letters, 2024 - Elsevier
Abstract The Fe-13Cr-4Al-2Mo-0.65 Nb alloy is being considered as a promising accident-
tolerant cladding fuel material for light water reactors design. The present work investigated …

High-Temperature Tensile Properties and Serrated Flow Behavior of FeCrAl Alloy for Accident-Tolerant Fuel Cladding.

M Chai, Z Han, H Su, H Li, P Liu… - Applied Sciences (2076 …, 2024 - search.ebscohost.com
The development of FeCrAl alloys has commenced for use as nuclear fuel cladding material,
intended to serve as an enhanced accident-tolerant alternative to Zr-based alloys. In this …

[图书][B] High-Temperature Mechanical Properties of Accident-Tolerant Fuel Cladding Materials

HS Abouelella - 2023 - search.proquest.com
This thesis is on the creep behavior of high Cr-containing FeCrAl Advanced Powder
Metallurgy Tubing (APMT) and 14YWT-NFA1 alloys. The observed APMT creep behavior …

Corrosion Behavior of Super-Ferritic Stainless Steels in NaCl Media

NS Zadorozne, JD Vier, RB Rebak, AE Ares - Characterization of Minerals …, 2017 - Springer
Recent worldwide demand has driven nickel and molybdenum prices to record high values.
Alloys containing significant amounts of nickel and molybdenum, such as the austenitic and …

Tensile Deformation Behavior of Al-rich Ferritic Steels for Advanced Light Water Reactors

A Guria, I Charit, B Petrovic - Frontiers in Materials Processing …, 2018 - Springer
Abstract Following the Fukushima Daiichi incident, there has been considerable interest in
developing accident-tolerant fuel cladding materials to make light water reactors (LWRs) …

Comportamiento frente a la corrosión de aceros inoxidables superferríticos en diferentes medios

A Krauchuka, J Vier, RS Rozicki, AE Ares, RB Rebak… - 2018 - rid.unam.edu.ar
El acero inoxidable del tipo 316 es uno de los más representativos dentro de los aceros
inoxidables austeníticos. Posee una buena resistencia a la corrosión y se lo emplea en …