Results 31 to 40 of about 843 (168)

Preliminary design of SiC composite cladding fuel rod with lead-bismuth eutectic filled pellet-cladding gap

open access: yesHe jishu
BackgroundThermal conductivity of SiC composite cladding significantly decreases after irradiation, leading to cladding failure due to high tensile stress under pellet-cladding mechanical interaction (PCMI).PurposeThis study aims to address the ...
ZHANG Ruixiao   +6 more
doaj   +1 more source

Effect of Ti and Si Interlayer Materials on the Joining of SiC Ceramics

open access: yesNuclear Engineering and Technology, 2016
SiC-based ceramic composites are currently being considered for use in fuel cladding tubes in light-water reactors. The joining of SiC ceramics in a hermetic seal is required for the development of ceramic-based fuel cladding tubes.
Yang-Il Jung   +5 more
doaj   +1 more source

Extrusion‐Based Additive Manufacturing of Advanced Ceramics: Strengthening Mechanisms and Process Optimization Review

open access: yesAdvanced Engineering Materials, Volume 28, Issue 16, 19 August 2026.
This review comprehensively evaluates extrusion‐based additive manufacturing for advanced ceramics, detailing feedstock options and key process parameters. By critically addressing defect mechanisms like porosity and cracking, the work highlights optimization strategies through machine learning and advanced postprocessing.
Meisam Bakhtiari   +4 more
wiley   +1 more source

Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions

open access: yesNuclear Engineering and Technology
FEMAXI-ATF is being developed for fuel performance modeling of SiC cladded UO2 fuel with focuses on modeling pellet-cladding mechanical interactions (PCMI). The code considers probability distributions of mechanical strengths of monolithic SiC (mSiC) and
Yoshihiro Kubo, Akifumi Yamaji
doaj   +1 more source

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

open access: yesThermo, 2021
Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop accident tolerant fuel (ATF) claddings for safety enhancement of light water reactors. Among many potential ATF
Hai V. Pham   +2 more
doaj   +1 more source

Applications of Textile Waste as Reinforcement in Fiber‐Reinforced Polymer Composites for Circularity—A Review

open access: yesMacromolecular Materials and Engineering, Volume 311, Issue 8, August 2026.
This review highlights the utilisation of textile waste in fibre‐reinforced polymer composites to reduce environmental impacts of pre‐ and post‐consumer textile waste. It critically examines waste composites’ manufacturing processes, their structural details, mechanical, thermal, physical properties, while discussing chemical treatments, hybridization ...
Md Ikramul Islam   +4 more
wiley   +1 more source

A Review of Failure Modes and Safety Strategies of Lithium‐Ion Batteries from Materials to Systems

open access: yesAdvanced Science, Volume 13, Issue 42, 28 July 2026.
A cascade‐aware framework is presented for lithium‐ion battery safety, linking thermal runaway initiation, acceleration, runaway reaction, and propagation with material‐, cell/pack‐, and system‐level interventions. By integrating failure mechanisms, quantitative safety indicators, and staged interception strategies, this review highlights how safer ...
Jin Hyeok Yang   +8 more
wiley   +1 more source

Microstructure and tribological properties of Co-Ti3SiC2 self-lubricating composite coatings on 304 stainless steel by laser cladding

open access: yesCailiao gongcheng, 2021
The self lubricating wear-resistant coatings were prepared on the surface of 304 stainless steel successfully using laser cladding synchronous powder feeding method, the ratio of cladding powder was pure Co, Co-2%Ti3SiC2(mass fraction, the same below ...
WANG Gang   +6 more
doaj   +1 more source

On the Conservatisms of Nepheline Predictors for Canister Centerline Cooled (CCC) High‐Level Waste (HLW) Glasses

open access: yesInternational Journal of Applied Glass Science, Volume 17, Issue 3, July 2026.
ABSTRACT Multiple models and feature sets have been generated, which attempt to predict the crystallization of nepheline (NaAlSiO4) in high‐level radioactive waste (HLW) glasses under canister centerline cooling (CCC) conditions. Earlier models were found to be overly conservative, while newer models had a not insignificant rate of false positives and ...
Jack D. Cornwall   +7 more
wiley   +1 more source

AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

open access: yesNuclear Engineering and Technology, 2018
AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to long-term revolutionary (SiC/SiC composite cladding ...
Jeremy Bischoff   +10 more
doaj   +1 more source

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