Results 21 to 30 of about 1,923 (185)
He jishu, 2023 BackgroundDuring reactor operation, zirconium (Zr) alloy cladding is continuously oxidized as it gets in contact with fuel, and combines with the fuel to form a firm chemical interaction layer.
WANG Huacai +5 more
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Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core
Energies, 2022 The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific thermomechanical properties. The aim of this study is to evaluate the neutronics performance of a chromium
Mohammad Alrwashdeh, Saeed A. Alameri
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Mechanical Engineering Journal, 2021 Pellet-Cladding Mechanical Interaction (PCMI) failure is one of the failure mode which must be evaluated in nuclear fuel safety. PCMI is caused by mechanical load to the cladding due to fuel pellet expansion.
Yuma HIGASHI +3 more
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Nuclear 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
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Understanding the interface interaction between U3Si2 fuel and SiC cladding
Nature Communications, 2020 Triuranium disilicide fuel and silicon carbide cladding system is of importance for accident tolerance fuel initiative. Here the authors discuss the role of interface interaction between the U3Si2 fuel and SiC cladding in their use as an advanced concept
Vancho Kocevski +3 more
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Behavior of Zircaloy Fuel Cladding Tubes [PDF]
Journal of Nuclear Science and Technology, 1976 A series of experiments has been performed to obtain information on the behavior of zircaloy fuel cladding tube, indispensable for predicting fuel performance in water reactors.
MAKI, Hideo, OOYAMA, Masatoshi
openaire +1 more source
Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor [PDF]
International Journal of Advanced Design and Manufacturing Technology, 2018 In the present study, investigation of mechanical behaviour of the fuel cladding material for a nuclear superheat Boiling Water Reactor with annular fuel rods, is carried out.
Majid Bahonar +2 more
doaj
Phase Engineering of Nanomaterials (PEN): Evolution, Current Challenges, and Future Opportunities
Advanced Materials, EarlyView.This review summarizes the synthesis, phase transition, advanced characterization spanning ex situ to in situ and operando techniques, and diverse applications of phase engineering of nanomaterials (PEN). It further outlines key challenges and future opportunities, such as phase stability, architecture control, and artificial intelligence (AI)‐driven ...
Ye Chen +7 more
wiley +1 more source
EPJ Nuclear Sciences & Technologies, 2016 Early pressurized water reactors were originally designed to operate using stainless steel as cladding material, but during their lifetime this material was replaced by zirconium-based alloys.
Giovedi Claudia +3 more
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Nuclear Engineering and Technology, 2020 A methodology for evaluation of mechanical and thermal effects of localized non-axisymmetric oxidation in zircaloy claddings on LWR fuel reliability is proposed. To this end, the basic capabilities of the FALCON fuel behaviour code are used.
Grigori Khvostov
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