Investigations of boron transport in a PWR core with COBAYA3/SUBCHANFLOW inside the NURESIM platform
暂无分享,去创建一个
[1] N. García-Herranz,et al. The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations , 2007 .
[2] E. Fridman,et al. Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR , 2011 .
[3] Juan Andrés Lozano Montero. Desarrollo de un código nodal analítico de difusión neutrónica en multigrupos para reactores nucleares en geometrías 3d rectangulares y hexagonales , 2010 .
[4] N. García-Herranz,et al. The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis , 2008 .
[5] R. Riggs,et al. Prioritization of generic safety issues , 1983 .
[6] Soeren Kliem,et al. Coupling of the neutron-kinetic core model DYN3D with the thermal hydraulic code FLICA-4 within the NURESIM platform , 2010 .
[7] Soeren Kliem,et al. Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR , 2012 .
[8] Thomas J. Downar,et al. High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor , 2007 .
[9] Manuel Calleja Reyna. Improvements in Multi-physics and Multi-scale Methodologies for Safety-related Investigations of Pressurized Water Reactors within the NURESIM Platform , 2013 .
[10] Sören Kliem. Ein Modell zur Beschreibung der Kühlmittelvermischung und seine Anwendung auf die Analyse von Borverdünnungstransienten in Druckwasserreaktoren , 2010 .
[11] Soeren Kliem,et al. Experiments at the mixing test facility ROCOM for benchmarking of CFD codes , 2008 .
[12] B. P. Leonard,et al. The ULTIMATE conservative difference scheme applied to unsteady one-dimensional advection , 1991 .
[13] I. Toumi,et al. FLICA-4: a three-dimensional two-phase flow computer code with advanced numerical methods for nuclear applications , 2000 .
[14] Uwe Imke,et al. Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT) , 2012 .
[15] Robert Stieglitz,et al. A coupled neutronic/thermal-hydraulic scheme between COBAYA3 and SUBCHANFLOW within the NURESIM simulation platform , 2012 .