Results 41 to 50 of about 1,620 (263)

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

open access: yesEPJ 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   +7 more
doaj   +1 more source

Versatile Pneumatic Twisted Coiled Actuators Enabled by Fiber‐Polymer Composite Fabrication

open access: yesAdvanced Functional Materials, EarlyView.
This work reports composite Pneumatic Twisted Coiled Actuators with embedded Kevlar fibers that convert pneumatic or hydraulic pressure into powerful linear motion. A novel precise manufacturing technique is used to systematically explore how design variables influence actuator mechanics and dynamics.
William J. Townsend   +5 more
wiley   +1 more source

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

open access: yesNuclear 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   +3 more
doaj   +1 more source

An Electrowetting Pump

open access: yesAdvanced Functional Materials, EarlyView.
A tubular electrowetting pump moves alternating droplets through a millimeter‐wide channel in discrete, reversible steps, functioning as a fluidic stepper motor. With no moving parts and electrodes insulated from the liquid, it delivers silent, accurate flow. Flexibility allows the pump to be woven directly into textiles for wearable, medical, and soft‐
Robert Hennig, Herbert Shea
wiley   +1 more source

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

open access: yesNuclear 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   +2 more
doaj   +1 more source

Cellular Responses to Mechanical Cues Across Scales: From Fundamental Insights to Translational Potential

open access: yesAdvanced Healthcare Materials, EarlyView.
This review examines how cellular behavior is regulated by mechanical cues transmitted through soft biomaterials, from single‐cell mechanosensing to tissue‐level adaptation. It highlights why physiological relevance, rather than model complexity alone, is critical for translational mechanobiology and introduces a scoring framework linking material ...
Mathias Polz   +9 more
wiley   +1 more source

ANALYSIS OF UNCERTAINTY QUANTIFICATION METHOD BY COMPARING MONTE-CARLO METHOD AND WILKS’ FORMULA

open access: yesNuclear Engineering and Technology, 2014
An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation has been performed and compared with the tolerance level determined by the Wilks’ formula.
SEUNG WOOK LEE   +3 more
doaj   +1 more source

Rapid Fabrication of Self‐Propelled and Steerable Magnetic Microcatheters for Precision Medicine

open access: yesAdvanced Materials, EarlyView.
A rapid Joule heating fabrication method for the production of self‐propelling, adaptive microcatheters, with tunable stiffness and integrated microfluidic channels is presented. Demonstrated through three microrobotic designs, including a steerable guiding catheter, an untethered wave‐crawling TubeBot, and a distal‐end propelled microcatheter, it was ...
Zhi Chen   +5 more
wiley   +1 more source

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

open access: yesNukleonika, 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

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

open access: yesNuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian   +11 more
doaj   +1 more source

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