Results 71 to 80 of about 843 (168)
Neutronic analysis of accident tolerant fuel concepts in spectral shift regulation conditions
The study of Accident Tolerant Fuels (ATFs) has gained significant attention due to their potential to enhance the safety and reliability of nuclear reactors, especially under severe accident conditions.
Tuymurodov Dilmurod +3 more
doaj +1 more source
Multiphysics Model Development and the Core Analysis for In Situ Breeding and Burning Reactor
The in situ breeding and burning reactor (ISBBR), which makes use of the outstanding breeding capability of metallic pellet and the excellent irradiation-resistant performance of SiCf/SiC ceramic composites cladding, can approach the design purpose of ...
Shengyi Si
doaj +1 more source
Hermeticity testing of SiC/SiC composite cladding tubes under internal pressure loading
The application of SiC fiber-reinforced SiC/SiC composites as pressurized water reactor (PWR) fuel cladding remains under investigation. In order to measure composite hermeticity under conditions more representative of PWRs, an in-situ internal pressure loading hermeticity test system was developed and relevant test configurations were identified.
Weijun Wang +6 more
openaire +1 more source
In the present work, predictive modelling and optimization with the adaptive network based fuzzy inference system (ANFIS) modelling of the mechanical properties of laser-coated NB/SiC/Ni welds was studied based on the Taguchi design by laser cladding. An
Zhe Zou, Juan Chen, Ming-Der Jean
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Accident Tolerant Fuel (ATF) technologies have emerged in response to the safety limitations of conventional UO2-Zr fuel systems in light water reactors (LWRs), particularly under high-temperature accident conditions, as highlighted by severe nuclear ...
Furkan Tayboga, Weiyan Yang, Kan Wang
doaj +1 more source
Methodology for Irradiation Creep Testing of SiC / SiC Composite Cladding [PDF]
Patrick Champlin +2 more
openaire +1 more source
R & D of SiC/SiC Fuel Cladding for Ultra-Safe Nuclear Reactors
Kishimoto, Hirotatsu +4 more
+5 more sources
Issue Update to LWR SiC/SiC Cladding Handbook of Properties [PDF]
Takaaki Koyanagi +3 more
openaire +1 more source
GIFT-1.0: Advanced light water reactor fuel performance code
In response to emerging fuel technologies, such as Accident Tolerant Fuels (ATF), Small Modular Reactor (SMR) fuels, and extended spent fuel storage in the nuclear power industry, GIFT-1.0 was developed to enable full life-cycle simulations of Light ...
Kyuseok Shim +4 more
doaj +1 more source
HFIR SiC-SiC Composite Clad Tube Bowing Test: Pre-Irradiation Characterization [PDF]
Josina Geringer +5 more
openaire +1 more source

