Results 11 to 20 of about 843 (168)

Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions

open access: yesEnergies, 2022
Our aim is to study the neutronic behaviour of potential accident-tolerant fuel (ATF) claddings in a pressurised water reactor under normal operations. This work compares ATF silicon carbide composite (SiC/SiC) cladding to conventional ZIRLOTM cladding ...
Maithah M. Alaleeli   +2 more
doaj   +1 more source

Three-Dimensional Modeling of Thermal-Mechanical Behavior of Accident Tolerant Fuels

open access: yesFrontiers in Energy Research, 2021
Considering the safety issues of the traditional UO2-Zr fuel, a variety of accident-tolerant fuel (ATF) candidates have been proposed in recent years.
Zitao Zeng   +9 more
doaj   +1 more source

Failure probability calculations of silicon carbide composite claddings under loss-of-coolant accidents

open access: yesHe jishu, 2023
BackgroundSilicon carbide (SiC) composite claddings are candidate solutions for accident resistant fuel claddings in light water reactors.PurposeThis study aims to estimate the failure probability of a double-layer structured SiC cladding under a loss-of-
CAO Liwen, YI Boquan, HAO Zulong
doaj   +1 more source

In-pile performance of end plug with different structure for SiC cladding

open access: yesFrontiers in Materials, 2023
The in-pile performance of SiC cladding with different kinds of end plug were studied. The effect of end plug structure on the mechanical performance of cladding was investigated.
Huifang Yue   +5 more
doaj   +1 more source

Investigation of the safety features of advanced PWR assembly using SiC, Zr, FeCrAl and SS-310 as cladding materials

open access: yesScientific Reports, 2021
In this work, SiC (Silicon carbide), FeCrAl (ferritic), SS-310 (stainless steel 310) and Zirconium are simulated by MCNPX (Monte Carlo N‐Particle eXtended) code as cladding materials in advanced PWR (Pressurized Water Reactor) assembly.
Sayed. Saeed. Mustafa
doaj   +1 more source

Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation

open access: yesEnergies, 2023
Silicon carbide (SiC) ceramic matrix composite (CMC) cladding is currently being pursued as one of the leading candidates for accident-tolerant fuel (ATF) cladding for light water reactor applications. The morphology of fabrication defects, including the
Fei Xu   +8 more
doaj   +1 more source

Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings

open access: yesMetals, 2018
The thermophysical performance and solid mechanics behavior of UO2-36.4vol % BeO fuel pellets cladded with Zircaloy, SiC, and FeCrAl, and Zircaloy cladding materials coated with SiC and FeCrAl, are investigated based on simulation results obtained by the
Wei Zhou, Wenzhong Zhou
doaj   +1 more source

Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials

open access: yesNuclear Engineering and Technology, 2021
Dual-cooled annular fuel allows a significant increase in power density while maintaining or improving safety margins. However, the dual-cooled design brings much higher Zircaloy charge in reactor core, which could cause a great threaten of hydrogen ...
Yangbin Deng   +7 more
doaj   +1 more source

Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident

open access: yesEnergies, 2018
In this study, we aim to conduct structural analyses of cladding materials, such as silicon carbide and zircaloy-4, during a Large-Break Loss-of-Coolant Accident.
Kwangwon Ahn, Kyohun Joo, Sung-Pil Park
doaj   +1 more source

Joining of SiC ceramics using high-silicon aluminum alloy fillers assisted by laser cladding

open access: yesJournal of Materials Research and Technology, 2023
A Si–40Al joining transition layer was prepared via laser cladding, followed by brazing of SiC ceramics using Si–60Al alloy as the joint filler. The microstructure, composition, and flexural strength of the brazed joints were investigated under different
Chang-Cong Huang   +4 more
doaj   +1 more source

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