Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor-Reference-Cited by-同舟云学术

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Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor

Published:2023-09 Issue: Volume:189 Page:109839
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ványi A.Sz.^ORCID,Hursin M.^ORCID,Aszódi A.,Adorján L.^ORCID,Biró B.^ORCID,Magyar B.^ORCID,Mészáros P.,Bozsó T.,Czifrus Sz.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE;Clifford;Nucl. Eng. Des.,2021

2. Natural Circulation in Water Cooled Nuclear Power Plants;IAEA,2005

3. Advances in Small Modular Reactor Technology Developments;IAEA,2020

4. NuScale small modular reactor for Co-generation of electricity and water;Ingersoll;Desalination,2014

5. Mechanical Design of BME TR Spent Fuel Transportation;Kovács,2011

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. Assessment of the research reactors in opposition to severe accidents;Nuclear Engineering and Design;2023-12

2. Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor;Annals of Nuclear Energy;2023-12

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