Zobrazeno 1 - 10
of 339
pro vyhledávání: '"Merzari, Elia"'
Autor:
Min, Misun, Lan, Yu-Hsiang, Fischer, Paul, Merzari, Elia, Nguyen, Tri, Yuan, Haomin, Shriwise, Patrick, Kerkemeier, Stefan, Davis, Andrew, Dubas, Aleksandr, Eardly, Rupert, Akers, Rob, Rathnayake, Thilina, Warburton, Tim
We discuss pioneering heat and fluid flow simulations of fusion and fission energy systems with NekRS on exascale computing facilities, including Frontier and Aurora. The Argonne-based code, NekRS, is a highly-performant open-source code for the simu
Externí odkaz:
http://arxiv.org/abs/2409.19119
Heat pipes can efficiently and passively remove heat in nuclear microreactors. Nevertheless, the flow dynamics within heat pipes present a significant challenge in designing and optimizing them for nuclear energy applications. This work aims to explo
Externí odkaz:
http://arxiv.org/abs/2408.02234
Autor:
Dutra, Carolina Bourdot, Merzari, Elia
Understanding the coolant thermal hydraulics in rod bundles is essential to the design of nuclear reactors. However, flows with low Reynolds numbers present serious modeling challenges, especially in heat transfer and natural convection. They are dif
Externí odkaz:
http://arxiv.org/abs/2308.15561
Autor:
Dutra, Carolina Bourdot, Merzari, Elia
The study of coolant flow behavior in rod bundles is of relevance to the design of nuclear reactors. Although laminar and turbulent flows have been researched extensively, there are still gaps in understanding the process of laminar-turbulent transit
Externí odkaz:
http://arxiv.org/abs/2308.15548
Autor:
Okyay, Sinan, Merzari, Elia, Reger, David A., Leite, Victor Coppo, Giudicelli, Guillaume, German, Peter, Lindsay, Alexander
Nuclear power is a significant source of electricity in the United States, but the average U.S. nuclear power plant is around 40 years old. Safe management of spent nuclear fuel (SNF) is a crucial aspect of the back end of the nuclear fuel cycle. SNF
Externí odkaz:
http://arxiv.org/abs/2308.15455
Wall channeling is a phenomena of interest for Pebble Bed Reactors (PBRs) where flow is diverted into high-porosity regions near the wall. This diversion of flow can have a significant impact on maximum fuel temperatures and core bypass flow. Porous
Externí odkaz:
http://arxiv.org/abs/2308.05031
Autor:
Nguyen, Tri, Merzari, Elia
The design of advanced nuclear reactors (Gen IV) involves an array of challenging fluid-flow issues that affect its safety and performance. The calculated DNS database will be instrumental in understanding the flow behavior in the downcomer. Ultimate
Externí odkaz:
http://arxiv.org/abs/2304.04085
Autor:
Nguyen, Tri, Merzari, Elia
Publikováno v:
ASME. J. Heat Transfer. July 2021; 143(7): 072601
Single-phase natural circulation thermosiphon loops have been attracting increased interest as they represent the prototype of passive safety systems. However, the stability properties of thermosiphon loops, which can affect and compromise their func
Externí odkaz:
http://arxiv.org/abs/2304.03404
In this paper, we propose a novel reduced order model (ROM) lengthscale that is constructed by using energy distribution arguments. The new energy-based ROM lengthscale is fundamentally different from the current ROM lengthscales, which are built by
Externí odkaz:
http://arxiv.org/abs/2211.04404
Buoyancy effect on low-flow condition convective heat transfer of non-conventional coolants, such as liquid metal and molten salts, is a crucial safety factor to advanced reactors under transient or accidental scenarios. The distinct heat transfer ch
Externí odkaz:
http://arxiv.org/abs/2204.00430