Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis
暂无分享,去创建一个
[1] Kostadin Ivanov,et al. Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models , 2006 .
[2] N. García-Herranz,et al. Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP-5 , 2004 .
[3] Carol Ahnert,et al. 3D WHOLE CORE FINE MESH MULTIGROUP DIFFUSION CALCULATIONS BY DOMAIN DECOMPOSITION THROUGH ALTERNATE DISSECTIONS , 2007 .
[4] L. J. Siefken,et al. FRAP-T6: a computer code for the transient analysis of oxide fuel rods. [PWR; BWR] , 1983 .
[5] M. Avramova,et al. Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses , 2006 .
[6] E. Royer,et al. LWR MULTI-PHYSICS DEVELOPMENTS AND APPLICATIONS WITHIN THE FRAMEWORK OF THE NURESIM EUROPEAN PROJECT , 2007 .
[7] D. D. Lanning,et al. FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup , 1997 .
[8] Nuria García Herranz,et al. Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system , 2008 .
[9] Kostadin Ivanov,et al. Nodal kinetics model upgrade in the Penn State coupled TRAC/NEM codes , 1999 .
[10] Tomasz Kozlowski,et al. Analysis of results for the OECD/NEA and U.S. NRC PWR MOX/UO 2 core transient benchmark , 2003 .
[11] N. García-Herranz,et al. The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations , 2007 .