Results 11 to 20 of about 690 (201)

LEU+ loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme

open access: yesNuclear Engineering and Technology, 2023
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU + has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4–5 w/o UO2 fuel.
Husam Khalefih   +3 more
doaj   +1 more source

Accident Tolerant Fuel Analysis [PDF]

open access: yes, 2014
Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension.
Curtis Smith   +5 more
openaire   +1 more source

Material Selection for Accident Tolerant Fuel Cladding [PDF]

open access: yesMetallurgical and Materials Transactions E, 2015
Alternative cladding materials to Zr-based alloys are being investigated for accident tolerance, which can be defined as >100X improvement (compared to Zr-based alloys) in oxidation resistance to steam or steam-H2 environments at ≥1473 K (1200 °C) for short times.
B. A. Pint   +3 more
openaire   +1 more source

On the oxidation mechanism of U3Si2 accident tolerant nuclear fuel

open access: yesCorrosion Science, 2020
The oxidation mechanism and products of U3Si2 accident tolerant nuclear fuel in flowing air up to 750C is reported. Differences between observed and theoretical mass gains for complete oxidation is due to un-oxidised Si that forms nano-crystalline regions of Si.
Harrison, Robert; id_orcid 0000-0003-1186-6056   +5 more
openaire   +1 more source

Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance

open access: yesNuclear Engineering and Technology, 2018
Accident-tolerant fuels (ATFs) are currently of high interest to researchers in the nuclear industry and in governmental and international organizations.
Martin Ševeček   +7 more
doaj   +1 more source

Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario

open access: yesBrazilian Journal of Radiation Sciences, 2021
Accident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and ...
Claudia Giovedi   +5 more
doaj   +1 more source

Fabrication of stoichiometric U3Si2 fuel pellets

open access: yesMethodsX, 2019
Uranium silicide, U3Si2, is an accident tolerant fuel type which is gaining momentum as a replacement fuel for uranium dioxide (UO2). Idaho National Laboratories has been fabricating phase pure U3Si2 fuel pellets for use in various irradiation and ...
Adrian R. Wagner   +5 more
doaj   +1 more source

Instability of U3Si2 in pressurized water media at elevated temperatures

open access: yesCommunications Chemistry, 2021
Uranium silicide is proposed as a highly accident tolerant light water reactor nuclear fuel, but its behavior under high-temperature, aqueous conditions is poorly studied.
Artaches Migdisov   +6 more
doaj   +1 more source

STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS

open access: yesActa Polytechnica CTU Proceedings, 2018
Coated cladding materials are considered as a near-term concept for so-called Accident Tolerant Fuel materials. Their behavior in accidental conditions is mainly studied around the world, however, they need to survive in-reactor normal operation before ...
Martin Ševeček   +2 more
doaj   +1 more source

Accident tolerant fuels to replace uranium dioxide

open access: yesJournal of Physics: Conference Series, 2020
Abstract The thermal conductivities for the traditional fuel UO2 and for the Accident Tolerant Fuel (uranium Molybdenum alloy, U-10Mo and uranium silicide, U3Si2) are calculated and compared. Then the temperature distributions on these core reactor, namely on the surface of the rod and in the center line of the rod were determined.
A Z Alhmoud, V B Kruglov, A B Kruglov
openaire   +1 more source

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