Upscaling and downscaling the heat transfer process coupled with neutronic reflected core for sodium-cooled fast nuclear reactor-Reference-Cited by-同舟云学术

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Upscaling and downscaling the heat transfer process coupled with neutronic reflected core for sodium-cooled fast nuclear reactor

Published:2022-06 Issue: Volume:189 Page:122713
ISSN:0017-9310
Container-title:International Journal of Heat and Mass Transfer
language:en
Short-container-title:International Journal of Heat and Mass Transfer

Author:

Pérez-Valseca A.D.,Espinosa-Paredes G.^ORCID,Aguilar-Madera C.G.^ORCID,Herrera-Hernández E.C.^ORCID,Gómez-Torres A.M.^ORCID

Publisher

Elsevier BV

Subject

Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics

Reference45 articles.

1. Nuclear Systems Volume II. Elements of Thermal Hydraulic Design;Todreas,2001

2. Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method;Gui;Prog. Nucl. Energy,2021

3. Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies;Sun;Prog. Nucl. Energy,2018

4. Subchannel analysis of annular fuel assembly using the preconditioned Jacobian-free Newton Krylov methods;Esmaili;Ann. Nucl. Energy,2020

5. Recent challenges in subchannel thermal-hydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction;Yang;Nucl. Eng. Des.,2019

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor;Nuclear Engineering and Design;2024-06

2. Heat transfer coefficients for bubbly molten salt nuclear reactors;Nuclear Engineering and Design;2023-12

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