3D space-time analysis of ATWS in compact high temperature reactor with integrated thermal-hydraulic model in code ARCH-TH

Author:

Dwivedi D.K.,Gupta Anurag,Kannan Umasankari

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference39 articles.

1. Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs;Aghaie;Ann. Nucl. Energy,2012

2. Boer, B., Lathouwers, D., Ding, M., Kloosterman, J.L., 2008. Coupled neutronics/thermal hydraulics calculations for High Temperature Reactors with the DALTON - THERMIX code system. International Conference on the Physics of Reactors, “Nuclear Power: A Sustainable Resource”. Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14–19.

3. A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors;Bonifetto;Nucl. Eng. Des.,2013

4. CFD analysis on heat transfer in low Prandtl number fluid flows;Borgohain;NURETH,2011

5. Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications;Cheng;Nucl. Eng. Des.,2006

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