An analysis of the pressure wave propagation by the sodium-water reaction in the printed circuit steam generator using the SWAAM-II code
Author:
Funder
National Research Foundation of Korea
Ministry of Science, ICT and Future Planning
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference24 articles.
1. Evaluation of a sodium-water reaction event caused by steam generator tubes break in the prototype generation IV sodium-cooled fast reactor;Ahn;Nucl. Eng. Tech,2016
2. The sensitivity analysis for IHTS and SG due to the large-scale Sodium-Water Reaction in PGSFR;Ahn;Ann. Nucl. Energy,2018
3. Comparative analysis of compact heat exchangers for application as the intermediate heat exchanger for advanced nuclear reactors;Bartel;Ann. Nucl. Energy,2015
4. Experimental and numerical study of a printed circuit heat exchanger;Chen;Ann. Nucl. Energy,2016
5. Cong, T., Wang, Z., Zhang, R., Wang, B., Zhu, Y., 2021. Thermal-hydraulic performance of a PCHE with sodium and sCO2 as working fluids. Ann. Nucl. Energy 157, 108210.
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1. Impingement wastage experiment with SUS 316 in a printed circuit steam generator;Nuclear Engineering and Technology;2024-01
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