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Št. zadetkov: 7
Random thermal loads in the thermal fatigue assessment of nuclear piping
Oriol Costa Garrido, Leon Cizelj, Iztok Tiselj
Doktorska disertacija
Oznake: material science;thermal fatigue;structural damage;nuclear safety;spectral methods;
Thermal fatigue is a structural damage mechanism which has been among the causes of reactor coolant leakages in nuclear power plants. A well-recognized source of thermal fatigue in the safety related nuclear piping is the turbulent mixing of fluids at different temperatures. The thermal fatigue ass ...
Leto: 2016 Vir: Fakulteta za matematiko in fiziko (UL FMF)
Divertor Tokamak Test facility project
F. Romanelli, Oriol Costa Garrido, Boštjan Končar, Patrik Tarfila, P. Zumbolo
Izvirni znanstveni članek
Oznake: jedrska fizika;jedrska tehnika;fizika plazme;
An overview is presented of the progress since 2021 in the construction and scientific programme preparation of the Divertor Tokamak Test (DTT) facility. Licensing for building construction has been granted at the end of 2021. Licensing for Cat. A radiologic source has been also granted in 2022. The ...
Leto: 2024 Vir: Institut Jožef Stefan (IJS)
Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Diego F. Mora, Oriol Costa Garrido, Roman Mukin, Markus Niffenegger
Izvirni znanstveni članek
Oznake:
Leto: 2020 Vir: Institut Jožef Stefan (IJS)
Structural analysis of DTT divertor PFU under electromagnetic and thermal loading
Patrik Tarfila, Oriol Costa Garrido, Boštjan Končar, Francesco Giorgetti, Selanna Roccella
Izvirni znanstveni članek
Oznake: termo mehanske analize;divertor;
The plasma-facing units (PFU) of the Divertor Tokamak Test facility (DTT) are expected to withstand high heat f luxes as well as electromagnetic (EM) loads during normal and off-normal operations. As the design of the DTT divertor PFU moves forward, specific analyses of the component’s real geometry ...
Leto: 2025 Vir: Fakulteta za matematiko in fiziko (UL FMF)
Structural integrity evaluation of the DTT plasma facing unit using detailed CFD and thermo-mechanical analyses
Patrik Tarfila, Oriol Costa Garrido, Boštjan Končar, Emanuela Martelli, Francesco Giorgetti, Selanna Rocella
Izvirni znanstveni članek
Oznake: jedrska fizika;jedrska tehnika;fizika plazme;
A new Divertor Tokamak Test (DTT) facility is currently being built in Italy to investigate different divertor configurations under different plasma scenarios. The divertor and in particular its target, consisting of Plasma Facing Units (PFUs), is exposed to high heat loads due to plasma fluence. In ...
Leto: 2024 Vir: Institut Jožef Stefan (IJS)
Replacement strategy of the EU-DEMO and CFETR breeding blanket pipes
Rocco Mozzillo, Christian Bachmann, Günter Janeschitz, Vincenzo Claps, Oriol Costa Garrido, Pan Hongtao, Fei Li, Donato Sorgente
Izvirni znanstveni članek
Oznake: fuzija;testni reaktorji;fusion;test reactors;remote maintenance;breeding blanket;feeding pipes;
Both EU-DEMO and CFETR need a workable replacement scheme for their tritium breeding blanket (BB). The radioactive environment dictates that all associated operations must be carried out through remotely controlled tools. Accessing and extracting the large BB segments requires their feeding pipes to ...
Leto: 2024 Vir: Institut Jožef Stefan (IJS)
Reaktorska tehnika
Leon Cizelj , Ivo Kljenak , Iztok Tiselj , Matjaž Leskovar , Oriol Costa Garrido , Raphael Connes , Zhengxiang Chen , S.TV.A.d.o.o.
Video in druga učna gradiva
Oznake: technology;energy;physics;nuclear physics
Raziskovalni program Reaktorska tehnika zajema raziskave na področju jedrske energije, tehnike in varnosti. Raziskujemo pojave, do katerih prihaja pri prehodnih pojavih, nezgodah in resnih nesrečah v jedrskih elektrarnah. Poleg tega, da prispevajo k jedrski varnosti, so rezultati raziskav uporabni t ...
Leto: 2013 Vir: videolectures.net
Št. zadetkov: 7
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