A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors-Reference-Cited by-同舟云学术

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A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors

Published:2020-07 Issue: Volume:125 Page:103369
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Wu Zeyun,Lu Cihang,Morgan Sarah,Bilbao y Leon Sama,Bucknor Matthew

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference68 articles.

1. Sodium thermal hydraulics in the pool LMFBR primary vessel;Azarian;Nucl. Eng. Des.,1990

2. Reduced Order Modeling of Fluid/structure Interaction;Barone,2009

3. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors;Bandini;Nucl. Eng. Des.,2015

4. Model development for analysis of the Korea advanced liquid metal reactor;Chang;Nucl. Eng. Des.,2002

5. Performance test of MARS-LMR code with benchmark analysis of EBR-II SHRT-17;Choi;Ann. Nucl. Energy,2016

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1. Numerical study on the characteristics of the LBE thermal stratification in a scaled-down hot pool;Annals of Nuclear Energy;2025-02

2. Analysis on thermal hydraulic characteristics for PHENIX natural circulation system using “1D system code + 3D CFD” simulation method;Progress in Nuclear Energy;2024-11

3. Performance and safety evaluation of a <10 wt% 235U enriched small lead-cooled fast reactor;Annals of Nuclear Energy;2024-09

4. 3D numerical simulation on thermal hydraulic characteristics in integrated sodium pool of PHENIX reactor during dissymmetric test;Annals of Nuclear Energy;2024-09

5. Numerical Simulation and Experimental Comparison of System Analysis Module 1D Mixing Model for Cold Shock Transients in the Gallium Thermal-Hydraulic Mixing Facility;Nuclear Technology;2024-07-10

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