Journal ArticleDOI
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
Reads0
Chats0
TLDR
In this paper, a comparison of a range of commercial and model alloys, conventional austenitic steels do not have sufficient oxidation resistance with only ∼18Cr-10Ni, and higher alloyed type 310 stainless steel is protective but Ni is not a desirable alloy addition for this application.About:
This article is published in Journal of Nuclear Materials.The article was published on 2013-09-01. It has received 356 citations till now. The article focuses on the topics: Alloy & Corrosion.read more
Citations
More filters
Journal ArticleDOI
Accident tolerant fuel cladding development: Promise, status, and challenges
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
Journal ArticleDOI
Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding
TL;DR: In this article, an application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed, based on specific limitations associated with zirconium alloys.
Journal ArticleDOI
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
TL;DR: In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.
Journal ArticleDOI
Current status of materials development of nuclear fuel cladding tubes for light water reactors
Zhengang Duan,Huilong Yang,Yuhki Satoh,Kenta Murakami,Sho Kano,Zishou Zhao,Jingjie Shen,Hiroaki Abe +7 more
TL;DR: In this paper, the impact of alloying elements on the material properties of Zirconium-based claddings has been systematically presented, including the impact on coating layer on the surface of Zr-based alloys, mainly referring coating materials and fabrication methods.
Journal ArticleDOI
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.
References
More filters
Journal ArticleDOI
Oxidation of 304 stainless steel in high-temperature steam
TL;DR: In this article, an experiment on oxidation of 304 stainless steel was performed in steam between 900°C and 1350°C, using the spare cladding of the reactor of the nuclear-powered ship Mutsu.
Journal ArticleDOI
Microstructure and impact properties of ferritic ODS ODM401 (14%Cr-ODS of MA957 type)
TL;DR: In this paper, the fracture surface was formed by alternated cleavage areas connected by inclined areas fractured by dimple micro mechanism proportional to the impact energy, and the temperature dependence of KLST impact energy was measured and transition temperature tDBTT evaluated about −110°C.
Journal ArticleDOI
Oxidation Behavior of ODS Fe-Cr Alloys
Bruce A. Pint,Ian G. Wright +1 more
TL;DR: In this paper, four experimental oxide dispersion strengthened ODSFe-(13−14 at. %)Cr ferritic alloys were exposed for up to 10,000 hr at 700-1100 °C in air and in air with 10vol.% water vapor.