Aluminum cladding oxidation of prefilmed in-pile fueled experiments
WR Marcum, DM Wachs, AB Robinson… - Journal of Nuclear …, 2016 - Elsevier
A series of fueled irradiation experiments were recently completed within the Advanced Test
Reactor Full size plate In center flux trap Position (AFIP) and Gas Test Loop (GTL) …
Reactor Full size plate In center flux trap Position (AFIP) and Gas Test Loop (GTL) …
The debris particles analysis of RSG GAS coolant to anticipate sediment induced corrosion
THE DEBRIS PARTICLES ANALYSIS OF RSG-GAS COOLANT TO ANTICIPATE SEDIMENT-
INDUCED CORROSION. The reliability of the structures, systems and components (SSC) of …
INDUCED CORROSION. The reliability of the structures, systems and components (SSC) of …
Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced Test Reactor—Oxide Growth Prediction and Correlation
Knowing the thickness of the oxide layer on the surface of aluminum fuel cladding is vitally
important for predicting fuel temperature due to the low thermal conductivity of the oxide …
important for predicting fuel temperature due to the low thermal conductivity of the oxide …
[PDF][PDF] Characterization of oxyhydroxides on a dry-stored fuel plate from L-Basin
L Olson, R Fuentes, A d'Entremont, R Sindelar - 2018 - sti.srs.gov
This report describes the characterization of oxyhydroxide (oxide) films on a fuel plate that
was previously irradiated in an RU-1 pool type reactor in Uruguay and subsequently stored …
was previously irradiated in an RU-1 pool type reactor in Uruguay and subsequently stored …
PLACA/DPLACA: Código para la simulación del comportamiento de un combustible tipo placa monolítico/disperso
A Soba, A Denis - … de métodos numéricos para cálculo y …, 2007 - upcommons.upc.edu
Se presentan los códigos PLACA/DPLACA desarrollados para la descripción del
comportamiento bajo irra-diación de elementos combustibles del tipo de los utilizados en …
comportamiento bajo irra-diación de elementos combustibles del tipo de los utilizados en …
Preliminary MITR Design-Demonstration Element Thermal-Hydraulics and Structural Analyses
ME Tano Retamales, SJ Yoon - 2022 - osti.gov
The United State High Performance Research Reactor (USHPRR) program aims to
eliminate more than 200kg of High Enriched Uranium (HEU) from commerce annually by …
eliminate more than 200kg of High Enriched Uranium (HEU) from commerce annually by …
Characterization of Oxide Growth of Aluminum Alloy 6061 for Nuclear Research and Test Reactors
Y Wei - 2015 - ir.library.oregonstate.edu
Oxide growth is a common phenomenon on aluminum alloy cladding surfaces in nuclear
research and test reactors. Without better understanding of oxide growth, excessive oxide …
research and test reactors. Without better understanding of oxide growth, excessive oxide …
Simulación del Comportamiento del Fluido Refrigerante en un Combustible Tipo Placa en el Código DIONISIO
ME Cazado, A Soba - Mecánica Computacional, 2021 - venus.santafe-conicet.gov.ar
El código de combustibles DIONISIO aproxima la termohidráulica del canal refrigerante
mediante modelos simples, unidimensionales. Sin embargo, los fenómenos que ocurren en …
mediante modelos simples, unidimensionales. Sin embargo, los fenómenos que ocurren en …
Experimental simulation of Al fuel plate oxidation
A Burkart, R Haddad, C Lafont, R Amoruso - 2009 - inis.iaea.org
[en] MTR fuel aluminium plates undergo oxidation in heat transfer conditions during
operation in Research or Production Reactors. The aluminium oxide is a poor thermal …
operation in Research or Production Reactors. The aluminium oxide is a poor thermal …
[PDF][PDF] AL PENGEMB
AN ENER, GI NUKLIR - 2016 - academia.edu
Volume 18, Nomor 1, Juni 2016 JURN AL PENGEMB ANG AN ENER GI NUKLIR Page 1 JPEN
Volume 18 Nomor 1 Hlm. 1 - 65 Jakarta Juni 2016 P-ISSN 1410-9816 Volume 18, Nomor 1, Juni …
Volume 18 Nomor 1 Hlm. 1 - 65 Jakarta Juni 2016 P-ISSN 1410-9816 Volume 18, Nomor 1, Juni …