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 …

[图书][B] Accident-tolerant materials for light water reactor fuels

RB Rebak - 2020 - books.google.com
Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …

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 …

Study of neutronic and creep properties of Kanthal APMT for advanced fuel cladding applications

A Pradhan, T Shrestha, CS Starr, TB McCall… - Progress in Nuclear …, 2024 - Elsevier
FeCrAl alloys have excellent oxidation resistance and exhibit slower reaction kinetics with
steam. Kanthal APMT is an advanced powder metallurgical FeCrAl alloy that shows promise …

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 …

Monotonous deformation behavior of ferritic FeCrAl alloy in the dynamic strain aging regime

Z Deng, J Liu, B Yan, Y He - Journal of Alloys and Compounds, 2018 - Elsevier
Monotonous deformation behavior of a ferritic FeCrAl alloy at a temperature range from
room temperature to 600° C was studied using the uniaxial tensile tests. The results showed …

Microstructure, mechanical properties and strengthening mechanisms of friction stir welded Kanthal APMT™ steel

A Sittiho, V Tungala, I Charit, RS Mishra - Journal of Nuclear Materials, 2018 - Elsevier
Abstract Kanthal APMT™ steel (Fe-22Cr-5Al-3Mo) is being investigated for possible use as
an accident-tolerant fuel cladding material in advanced light water reactors. Generally, high …

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 …

Role of refractory inclusions in the radiation-induced microstructure of APMT

D Zhang, SA Briggs, KG Field - Journal of Nuclear Materials, 2018 - Elsevier
Kanthal APMT is a promising FeCrAl-based alloy for accident-tolerant fuel cladding because
of its excellent high-temperature oxidation resistance. In this study, powder metallurgy …

典型事故容错轻水堆燃料包壳候选材料SiCf/SiC 复合材料和Mo 合金的研究进展

程亮, 张鹏程 - 材料导报, 2018 - mater-rep.com
摘要轻水堆是当前核电站应用最为广泛的堆型, 其包壳材料均为锆合金. 然而,
福岛严重核事故的突发, 使锆合金包壳的安全性受到质疑, 事故容错燃料及其包壳候选材料被提 …