, The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety Gyeongju, pp.11-320, 2016.
VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) Summary Results of Exercise 1 on Vessel Mixing Simulation, vol.10, 2010. ,
VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) Final Specifications of the VVER-1000 Vessel Mixing Problem, vol.22, 2007. ,
Simulation of mixing effects in a VVER-1000 reactor, vol.237, pp.1718-1728, 2007. ,
URL : https://hal.archives-ouvertes.fr/cea-02360106
Detailed CFX-5 study of the coolant mixing within the reactor pressure vessel of a VVER-1000 reactor during a non-symmetrical heat-up test, Nuclear Eng. Design, vol.238, issue.3, pp.445-452, 2008. ,
CFD-Calculation of Fluid Flow in a Pressurized Water Reactor, Journal of Sciences, Islamic Republic of Iran, vol.19, issue.3, pp.273-281, 2008. ,
SOLA-a numerical solution algorithm for transient flow, Los Alamos National Lab, 1975. ,
On the Stability and Convergence of Projection Methods Based on Pressure Poisson Equation, Int. J. Numer. Meth. Fluids, vol.26, pp.1039-1053, 1998. ,
Best Practice Guidelines for the Use of CFD in Nuclear Safety Applications, p.5, 2007. ,
Using the PIRT to represent application and validation domains for CFD studies, Proceedings of ICONE-23, vol.5, pp.17-21, 2015. ,
Improving confidence in CFD results for nuclear safety demonstration -Example of heterogeneous inherent boron dilution, Proceedings of ICONE-23, vol.5, pp.17-21, 2015. ,
, HANDBOOK OF HYDRAULIC RESISTANCE, 2008.
Analysis of the Natural Convection Flow in the Upper Plenum of the MONJU Reactor with Trio_U, Science and Technology of Nuclear Installations, vol.5, 2013. ,