Results 71 to 80 of about 288 (181)

Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors. [PDF]

Materials (Basel), 2023
Jia H, Wang Y, Wang Y, Han L, Zhang Y, Zhou Z.   +5 more
europepmc   +1 more source

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

Applied Sciences
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 study, the Fe-13Cr-4Al alloy, specifically designed for advanced accident-
Mengyu Chai, Zelin Han, Hao Su, Hao Li, Pan Liu, Yan Song   +5 more
doaj   +1 more source

A novel plasma-sprayed Cr/FeCrAl dual-layer coating on Zr alloy for potential high‐temperature applications

Journal of Materials Research and Technology
To better meet the requirements in loss-of-coolant accidents (LOCA) and conventional operating conditions in nuclear applications, this work prepared Cr, FeCrAl, and Cr/FeCrAl composite coatings on Zr alloys using plasma spraying technology.
Nan Li, Liang-Yu Chen, Linjiang Chai, Hao-Nan Xuan, Zexin Wang, Lina Zhang, Dubovyy Oleksandr, Jun Zhang, Sheng Lu   +8 more
doaj   +1 more source

In-situ synthesis of Yttria-based precipitates and their effects on Fe12Cr6Al in laser powder bed fusion

Journal of Materials Research and Technology
To advance the suitability of FeCrAl alloys for nuclear applications, radiation damage resistance, creep resistance, corrosion resistance, and mechanical properties enhancement are essential.
Omer Cakmak, Hwasung Yeom, Jung-Wook Cho
doaj   +1 more source

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Corrosion and Materials Degradation
The corrosion-resistant properties of IronChromium–Aluminum (FeCrAl) alloys have been known for nearly a century. Since the 1950s, they have been explored for application in the generation of nuclear power.
Haozheng Qu, Liang Yin, Michael Larsen, Raul B. Rebak   +3 more
doaj   +1 more source

Impact of silicon on neutronic performance and microstructural evolution of FeCrAl alloys for ATF cladding

EPJ Nuclear Sciences & Technologies
FeCrAl alloys are promising candidate for accident tolerant fuel (ATF) cladding in light water-cooled nuclear reactors (LWRs) due to their excellent high-temperature oxidation resistance and mechanical strength.
Ngarayana I. Wayan, Mulyana Dany, Andryansyah, Saragi Elfrida, Sony Tjahyani Damianus Toersiwi, Citra Amelia Almira, Farihin Parikin, Djuliana Safiya   +7 more
doaj   +1 more source

Estimation of adhesion energy of alumina scales on FeCrAl alloys: effect of the TiO2 sol-gel coating

MATEC Web of Conferences, 2013
In this experimental work, the effect of sol-gel TiO2 coating on adhesion energy of alumina scales formed on FeCrAl alloys was investigated. The adhesion energy was evaluated by means of a tensile test in the SEM chamber for the samples oxidized in air ...
Chegroune R., Keddam M.
doaj   +1 more source

Regulating heat input for additive manufacturing of oxide inclusions-free ODS-FeCrAl steel

Journal of Materials Research and Technology
Laser-based powder bed fusion (PBF-LB) of oxide dispersion strengthened (ODS)-FeCrAl steel commonly results in the generation of Y–Al–O oxide inclusions in the matrix.
Yanan Wang, Yan Peng, Binbin Wang, Baoxian Su, Liangshun Luo, Liang Wang, Yanqing Su, Jingjie Guo, Hengzhi Fu   +8 more
doaj   +1 more source

Overlay welding of FeCrAl alloys

, 2016
I detta examensarbete har olika påsvetsningsmetoder som är lämpliga för en pannapplikation undersökts. Syftet med denna studie var att undersöka både för- och nackdelar med påsvetsningsmetoderna och föreslå några utvärderingskriterier på vissa kommersiella och experimentella legeringar som lämpar sig för påsvetsningsmaterial.
openaire   +1 more source

Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments

npj Materials Degradation
Iron-Chromium-Aluminum (FeCrAl) alloys are candidate materials for the cladding of light water reactor (LWR) fuels. The FeCrAl alloys in general range in Cr composition from 12% (C26M) to 21% (APMT).
Rajnikant V. Umretiya, Haozheng Qu, Liang Yin, Timothy B. Jurewicz, Vipul K. Gupta, Marija Drobnjak, Michael P. Knussman, Andrew K. Hoffman, Raul B. Rebak   +8 more
doaj   +1 more source