Results 41 to 50 of about 1,398,280 (304)

Development of dynamic motion models of SPACE code for ocean nuclear reactor analysis

Nuclear Engineering and Technology, 2022
Lately, ocean nuclear power plants have attracted attention as one of diverse uses of nuclear power plants. Because ocean nuclear power plants are movable or transportable, it is necessary to analyze the thermal hydraulics in a moving frame of reference,
Byoung Jae Kim, Seung Wook Lee
doaj   +1 more source

Direct Metal Deposition of Graphene–Ti28Nb35.4Zr Matrix Composites With Enhanced Mechanical, Corrosion, and Biocompatibility Properties for Bone Implants

Advanced Engineering Materials, EarlyView.
Graphene nanoplatelet (0.1 wt.%) reinforcement significantly enhances the performance of β Ti‐28Nb‐35.4Zr alloy. Grain refinement, reduced water contact angle, and improved surface characteristics promote osteoblast adhesion and complete surface coverage after 7 days.
Khurram Munir, Jixing Lin, Yuncang Li, Li Zhu, Paul F. A. Wright, Cuie Wen   +5 more
wiley   +1 more source

Development and testing of the hydrogen behavior tool for Falcon – HYPE

Nuclear Engineering and Technology
The presence of hydrogen absorbed by zirconium-based cladding materials during reactor operation can trigger degradation mechanisms and endanger the rod integrity.
Piotr Konarski, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi   +3 more
doaj   +1 more source

Compatibility of Methacrylate Based Resins Controls Interfacial Failure and Toughness in 3D‐Printed Multimaterial Composites

Advanced Engineering Materials, EarlyView.
This work shows that the mechanical performance of multimaterial digital light processing (DLP) printed thermoset composites is governed by resin compatibility and interfacial design rather than spatial patterning alone. Brittle and ductile resin combinations produced premature interfacial failure, while graded interfaces and mechanically compatible ...
Ahmed M. H. Ibrahim, Li Meng, Ahmad R. Najafi, Nicolas J. Alvarez   +3 more
wiley   +1 more source

Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility

Nuclear Engineering and Technology
Passive safety systems are integrated into the latest generation of Light Water Reactors (LWRs), including small modular reactors. This paper employs the US-NRC TRACE thermal hydraulic code to examine the performance of a passive safety condenser known ...
Omar S. Al-Yahia, Ivor Clifford, Hakim Ferroukhi   +2 more
doaj   +1 more source

An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor [PDF]

EPJ Web of Conferences, 2019
The PETALE experimental programme in the CROCUS reactor at EPFL intends to contribute to the validation and improvement of neutron nuclear data in the MeV energy range for stainless steel, particularly in the prospect of heavy reflector elements of ...
Lamirand Vincent, Laureau Axel, Rochman Dimitri, Perret Gregory, Gruel Adrien, Leconte Pierre, Blaise Patrick, Pautz Andreas   +7 more
doaj   +1 more source

Modeling, Validation, Scaling, Uncertainty and Application in Nuclear Thermal Hydraulics

, 2022
Nuclear Thermal Hydraulics (NTH) implies a universe of knowledge, which, among the other things, is not easy to summarize and can be described (correctly) from different viewpoints.
D'Auria Francesco, Galassi G.
core  

Comparison of Triply Periodic Minimal Surface Energy Absorbers Under Uniaxial Compressive Loading

Advanced Engineering Materials, EarlyView.
This study investigates LCD 3D printed Triply Periodic Minimal Surface (TPMS) structures as mechanical energy absorbers. By comparing various base designs and layered combinations under uniaxial compression, it identifies that a Diamond‐Gyroid sandwich structure offers superior performance.
Sergej Grednev, Noah‐Lean Roschlaub, Anne Jung   +2 more
wiley   +1 more source

Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent

Nukleonika, 2015
Three-dimensional simulations of neutronics and thermal hydraulics of nuclear reactors are a tool used to design nuclear reactors. The coupling of MCB and FLUENT is presented, MCB allows to simulate neutronics, whereas FLUENT is computational fluid ...
Królikowski Igor P., Cetnar Jerzy
doaj   +1 more source

Coupled Monte Carlo and Thermal-Hydraulics Modeling for the Three-Dimensional Steady-State Analysis of the Xi’an Pulsed Reactor

Energies, 2023
The Xi’an Pulsed Reactor (XAPR) is characterized by its small core size and integrated fuel moderator structure, which results in a non-uniform core power and temperature distribution. Consequently, a complex coupling relationship exists between its core
Duoyu Jiang, Peng Xu, Tianliang Hu, Xinbiao Jiang, Lipeng Wang, Da Li, Xinyi Zhang, Lu Cao   +7 more
doaj   +1 more source