Verification of neutronics and thermal-hydraulics coupling method for FLUENT code using the MSRE pump startup, trip data-Reference-Cited by-同舟云学术

Verification of neutronics and thermal-hydraulics coupling method for FLUENT code using the MSRE pump startup, trip data

Published:2021-07 Issue: Volume:378 Page:111191
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mochizuki Hiroyasu

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

Reference25 articles.

1. ANSYS Inc., 2011. ANSYS Fluent Theory Guide, https://kargosha.com/file/attach/20175/2812.pdf.

2. Auwerda, G.J., 2007. Computational modeling of a molten salt reactor, BSc thesis of TU Delft. https://www.tudelft.nl/tnw/over-faculteit/afdelingen/radiation-science-technology/research/research-groups/reactor-physics-and-nuclear-materials/publications/bsc-theses/.

3. Ball, S.J., Kerlin, T.W., 1965. Stability analysis of the molten-salt reactor experiment, ORNL-TM-1070. http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-1070.pdf.

4. Bao, J., 2016. Development of the model for the multi-physics analysis of Molten Salt Reactor Experiment using Gen-Foam code, Master Thesis, Paul Scheller Institute. https://www.psi.ch/sites/default/files/import/fast/PublicationsEN/FB-DOC-16-014.pdf.

5. Briggs, R.B., 1964. Molten-salt reactor program semiannual progress report, ORNL-3708. https://technicalreports.ornl.gov/1964/3445600500358.pdf.

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