Results 41 to 50 of about 2,554,621 (223)

Evaluation of radioactive material leakage through the fuel cladding as result of diffusion processes during the long-term storage of spent nuclear fuel

open access: yesJournal of King Saud University: Engineering Sciences
Diffusion is regarded as one of mechanisms, which leads to leakages through the fuel cladding during the long-term storage of spent nuclear fuel. The schematization of the diffusion process through a circular cylindrical cladding of fuel elements, where ...
Svitlana Alyokhina   +2 more
doaj   +1 more source

Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions

open access: yesNuclear Engineering and Technology, 2020
A parametric study of several parameters relevant to design safety on the spent nuclear fuel (SNF) rod response under a drop accident is presented.
Belal Almomani   +3 more
doaj   +1 more source

Fire‐Safe Polymeric Insulation Foams for Energy‐Efficient and Low‐Carbon Buildings

open access: yesENERGY &ENVIRONMENTAL MATERIALS, EarlyView.
This review systematically summarizes recent advances in fire‐safe polymeric insulation foams, emphasizing the balance among flame retardancy, thermal insulation, mechanical reliability, and long‐term durability. By linking material‐level thermophysical properties with building cooling‐energy demand and operational carbon emissions, it establishes a ...
Qinhe Guo   +10 more
wiley   +1 more source

Review of aluminum solubility behavior in the Hanford 200 South West Area tanks targeted for retrieval

open access: yesEnvironmental Progress &Sustainable Energy, EarlyView.
Abstract The behavior of aluminum‐bearing phases in tank wastes from the southwest quadrant of the Hanford Site's 200 West Area primarily determines solids accumulation, retrieval performance, and downstream processability. This review synthesizes historical tank characterization data, laboratory dissolution studies, and process‐relevant observations ...
Brett C. Simpson   +2 more
wiley   +1 more source

Numerical Simulation Study on Chemical Interaction between UO2 Fuel and HT9 Cladding in Fast Reactors

open access: yesYuanzineng kexue jishu
This study aims to establish a numerical simulation method for analyzing the chemical interaction (FCCI, fuel-cladding chemical interaction) between UO2 fuel and HT9 ferritic-martensitic stainless steel cladding, providing a theoretical tool for ...
CHEN Nan1, HE Yanan1, ZHANG Jing1, WU Yingwei1, ZHOU Yi2, TIAN Wenxi1, QIU Suizheng1
doaj   +1 more source

The Effect of Scanning Strategies on FeCrAl Nuclear Thin-Wall Cladding Manufacturing Accuracy by Laser Powder Bed Fusion

open access: yesCrystals, 2022
FeCrAl alloy has been proposed as an alternative material for accident-tolerant fuel (ATF) cladding for nuclear reactors. Thin-wall cladding can be rapidly fabricated by laser powder bed fusion (LPBF). In this paper, a finite element model is established
Fusheng Cao   +9 more
doaj   +1 more source

Effect of Ammonium Polyphosphate/Silicate Content on the Postfire Mechanics of Epoxy Glass‐Fiber Composites Using Facile Chocolate Bar‐Inspired Structures

open access: yesFire and Materials, Volume 49, Issue 3, Page 329-346, April 2025.
ABSTRACT This study investigates the postfire mechanical properties of epoxy glass‐fiber reinforced composites (EP GFRCs) using increasing concentrations of ammonium polyphosphate (APP) and inorganic silicate (InSi) to modify the char and fire residue.
Sruthi Sunder   +5 more
wiley   +1 more source

A finite element approach for the implementation of magnetostrictive material terfenol-D in automotive CNG fuel injection actuation [PDF]

open access: yes, 2008
Magnetostriction is the deformation that spontaneously occurs in ferromagnetic materials when an external magnetic field is applied. In applications broadly defined for actuation, magnetostrictive material Terfenol-D possesses intrinsic rapid response ...
Choadhury, Habibullah Amin
core   +2 more sources

Heat and Mass Transfer during Hydrogen Generation in an Array of Fuel Bars of a BWR Using a Periodic Unit Cell

open access: yesScience and Technology of Nuclear Installations, 2012
This paper presents, the numerical analysis of heat and mass transfer during hydrogen generation in an array of fuel cylinder bars, each coated with a cladding and a steam current flowing outside the cylinders.
H. Romero-Paredes   +2 more
doaj   +1 more source

Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes

open access: yesNuclear Engineering and Technology, 2018
Different methods of axial and tangential testing and various sample geometries were investigated, and new test geometries were designed to determine the ultimate tensile strength of zirconium cladding tubes.
Márton Király   +3 more
doaj   +1 more source

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