Brazing SiC ceramics and Zr with CoCrFeNiCuSn high entropy alloy
CoCrFeNiCuSn high-entropy alloy and Cu foam composite interlayer was used as a filler for
the brazing of SiC ceramics and Zr. The microstructure and mechanical properties of the …
the brazing of SiC ceramics and Zr. The microstructure and mechanical properties of the …
Hydrogen diffusion in zirconium hydrides from on-the-fly machine learning molecular dynamics
Reactor pressure vessels and fuel cladding tubes have repeatedly failed due to zirconium
hydrides. Zirconium hydride precipitation and growth are directly affected by hydrogen atom …
hydrides. Zirconium hydride precipitation and growth are directly affected by hydrogen atom …
Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident
D Wang, Y Zhang, S Wu, GH Su, S Qiu, W Tian… - Journal of Nuclear …, 2022 - Elsevier
Abstract During Loss of Coolant Accident (LOCA) in Pressurized Water Reactor (PWR), the
oxidation of zirconium alloy cladding has a significant impact on the core degradation …
oxidation of zirconium alloy cladding has a significant impact on the core degradation …
Hydrogen distribution in a BWŔs RPV and Mark II drywell during the progression of a severe accident with and without emergency coolant injection
J Ortiz-Villafuerte, E Sáinz-Mejía… - … Engineering and Design, 2024 - Elsevier
This study is directed to determine potential risks associated to hydrogen concentrations in
an originally fully inertized drywell of a BWR Mark II primary containment, as a consequence …
an originally fully inertized drywell of a BWR Mark II primary containment, as a consequence …
Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process
JH Jo, JH Choi, JW Kim, DJ Kim… - International Journal of …, 2024 - Wiley Online Library
Nuclear accidents, such as the Fukushima nuclear accident, have highlighted the necessity
for accident‐tolerant fuel (ATF) cladding. Previous studies focused on coating the outside of …
for accident‐tolerant fuel (ATF) cladding. Previous studies focused on coating the outside of …
Machine learning-based mechanical properties estimation and structural integrity assessment of SNF cladding under hypothetical drop accident conditions
YG Shin, B Almomani, YS Chang - Nuclear Engineering and Design, 2025 - Elsevier
The nuclear fuel cladding must perform its inherent function as a radiation shield throughout
the entire process from in-reactor operation to transportation, storage and disposal …
the entire process from in-reactor operation to transportation, storage and disposal …
Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel
Z Kowsar, A Zolfaghari, M Zamzamian… - Annals of Nuclear …, 2023 - Elsevier
In this paper, the modeling of fission gases, particularly xenon and krypton, and their effects
on the thermal performance with application to UO 2-zirconium dispersion fuel is …
on the thermal performance with application to UO 2-zirconium dispersion fuel is …
Feasibility Study on Thickness Measurement of Coated ZrO2 Using Optical Coherence Tomography
J Li, Y Ding, T Zhao, C Lei, L Bai - 2023 9th International …, 2023 - ieeexplore.ieee.org
ZrO 2 is coated on nuclear fuel rod to protect it from high temperature steam oxidation and
erosion, the degeneracy of the coated ZrO_2 is inevitable and needs to be measured in-situ …
erosion, the degeneracy of the coated ZrO_2 is inevitable and needs to be measured in-situ …