Predicting Large Deflections of Multiplate Fuel Elements Using a Monolithic FSI Approach
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Science and Engineering"
DOI: 10.1080/00295639.2017.1379304
Abstract: Abstract As part of the Global Threat Reduction Initiative, the Oak Ridge National Laboratory is evaluating conversion of fuel for the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium. Currently, multiphysics simulations… read more here.
Keywords: large deflections; predicting large; fuel elements; deflections multiplate ... See more keywords
Effect of ion polishing on corrosion resistance of the cladding of fuel elements from E110 alloy in the steam water environment
Sign Up to like & getrecommendations! Published in 2017 at "Inorganic Materials: Applied Research"
DOI: 10.1134/s207511331703011x
Abstract: The method of modification of the outer surface of the cladding of fuel elements from E110 Zr alloy by means of irradiation with a radial beam of Ar+ ions with a broad energy spectrum is… read more here.
Keywords: water; cladding fuel; fuel elements; ion ... See more keywords
The Electric Current Effect on Electrochemical Deconsolidation of Spherical Fuel Elements
Sign Up to like & getrecommendations! Published in 2017 at "Science and Technology of Nuclear Installations"
DOI: 10.1155/2017/2126876
Abstract: For High-Temperature Gas-Cooled Reactor in China, fuel particles are bonded into spherical fuel elements by a carbonaceous matrix. For the study of fuel failure mechanism from individual fuel particles, an electrochemical deconsolidation apparatus was developed… read more here.
Keywords: electrochemical deconsolidation; spherical fuel; fuel elements; fuel ... See more keywords
Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program
Sign Up to like & getrecommendations! Published in 2021 at "Science and Technology of Nuclear Installations"
DOI: 10.1155/2021/6686919
Abstract: The spherical fuel elements are adopted in the high-temperature gas-cooled reactor pebble-module (HTR-PM). The fuel elements will be discharged continuously from the reactor core and transported into the fuel transport pipelines during the reactor operation,… read more here.
Keywords: transport pipelines; fuel transport; transport; fuel elements ... See more keywords
THE METHOD FOR OPTIMIZING THE IRON CONTENT IN THE STRUCTURAL MATERIAL Zr1%Nb FOR FUEL ELEMENT CLADDING OF NPP NUCLEAR REACTORS
Sign Up to like & getrecommendations! Published in 2023 at "Problems of Atomic Science and Technology"
DOI: 10.46813/2023-144-046
Abstract: The mathematical method of optimizing the amount of the alloying element Fe in structural zirconium alloys Zr1%Nb of fuel elements cladding of nuclear reactor-cores of nuclear power plants on the basis of physical experiments to… read more here.
Keywords: method optimizing; fuel; fuel elements; zr1 fuel ... See more keywords