Validation of the STEG code using experiments on Two-Phase flow across horizontal tube bundles-Reference-Cited by-同舟云学术

Validation of the STEG code using experiments on Two-Phase flow across horizontal tube bundles

Published:2022-12 Issue: Volume:399 Page:112048
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Liu Shixian^ORCID,Yin Fei^ORCID,Melikhov V.I.,Melikhov O.I.

Funder

Russian Science Foundation

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference45 articles.

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3. The influence of void fraction on the submerged perforated sheet hydraulic friction factor;Blinkov;Therm. Eng.,2015

4. Influence of non-uniformity of the submerged perforated sheet on steam demand leveling on the evaporation surface of a WWER steam generator;Blinkov;Therm. Eng.,2016

5. Drift flux modeling of the VVER-1000 horizontal nuclear steam generator;Ghazanfari;Prog. Nucl. Energy,2014

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1. Validation of the STEG Code against Experimental Data on Hydrodynamics of a Horizontal Steam Generator;Thermal Engineering;2024-05

2. Modeling of Two-Phase Flow Using STEG Code with Module for Calculating Interfacial Area Transport;2024 6th International Youth Conference on Radio Electronics, Electrical and Power Engineering (REEPE);2024-02-29

3. Simulation of the two-phase flow through the hole of the submerged perforated sheet;2023 5th International Youth Conference on Radio Electronics, Electrical and Power Engineering (REEPE);2023-03-16