Results 81 to 90 of about 647 (119)
Entwicklung einer Version des Reaktordynamikcodes DYN3D für Hochtemperaturreaktoren
, 2012 Rohde, U. +7 more
openaire +1 more source
Some of the next articles are maybe not open access.
Related searches:
Related searches:
Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
Kerntechnik, 2012Abstract RUTA-70 model for simulations with the internally coupled codes DYN3D/ATHLET and DYN3D/RELAP5 was developed. A 3-D power distribution in the core is calculated by DYN3D with thermal-hydraulic feedback from the system codes. A steady-state corresponding to the full reactor power and an accident scenario initiated by failure of ...
Kozmenkov, Y. +3 more
+9 more sources
Annals of Nuclear Energy, 2018
Abstract A comparative study has been performed to evaluate the prediction capability of the DYN3D-Serpent code system for sodium fast reactor (SFR) cores. In this study, the calculation system was tested against the BFS-73-1 and BFS-62-3A experiments conducted at the Russian Institute of Physics and Power Engineering (IPPE).
Reuven Rachamin, Soeren Kliem
exaly +3 more sources
Abstract A comparative study has been performed to evaluate the prediction capability of the DYN3D-Serpent code system for sodium fast reactor (SFR) cores. In this study, the calculation system was tested against the BFS-73-1 and BFS-62-3A experiments conducted at the Russian Institute of Physics and Power Engineering (IPPE).
Reuven Rachamin, Soeren Kliem
exaly +3 more sources
Modeling of SFR cores with Serpent–DYN3D codes sequence
Annals of Nuclear Energy, 2013Abstract DYN3D reactor dynamics nodal diffusion code was originally developed for the analysis of Light Water Reactors. In this paper, we demonstrate the feasibility of using DYN3D for modeling of fast spectrum reactors. A homogenized cross sections data library was generated using continuous energy Monte-Carlo code Serpent which provides significant
Emil Fridman, Eugene Shwageraus
exaly +3 more sources
The reactor dynamics code DYN3D
Kerntechnik, 2016Abstract The article provides an overview on the code DYN3D which is a three-dimensional core model for steady-state, dynamic and depletion calculations in reactor cores with quadratic or hexagonal fuel assembly geometry being developed by the Helmholtz-Zentrum Dresden-Rossendorf for more than 20 years.
S. Kliem +7 more
openaire +1 more source
The reactor dynamics code DYN3D – models, validation and applications
Progress in Nuclear Energy, 2016Abstract The article provides an overview of the reactor dynamics code DYN3D. The code comprises various 3D neutron kinetics solvers, a thermal-hydraulics reactor core model and a thermo-mechanical fuel rod model. The implemented models and methods and the capabilities and features of the code are described.
Soeren Kliem +2 more
exaly +3 more sources
Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D
Nuclear Science and Engineering, 2004The OECD/NRC Boiling Water Reactor (BWR) Turbine Trip Benchmark was analyzed by the code DYN3D and the coupled code system ATHLET/DYN3D.
Grundmann, U., Kliem, S., Rohde, U.
openaire +2 more sources
Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes
Annals of Nuclear Energy, 2013Abstract In this study, HELIOS-2 deterministic transport code and Serpent Monte–Carlo (MC) reactor physics code were considered as tools for preparation of few-group constants for sodium cooled fast reactor (SFR) analysis. Initially, applicability of the mainly LWR-oriented HELIOS-2 code to the modeling of SFR lattices was investigated and ...
Reuven Rachamin, Emil Fridman
exaly +3 more sources
DYN3D-MSR spatial dynamics code for molten salt reactors
Annals of Nuclear Energy, 2007Abstract The development of spatial dynamics code for molten salt reactors (MSRs) is reported in this paper. The graphite-moderated channel type MSR – one of the ‘Generation IV’ concepts – was selected for the numerical simulation. It has several peculiarities (e.g. the drift of delayed neutrons precursors), which disable the use of standard dynamics
Krepel, J. +3 more
openaire +2 more sources
ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
Annals of Nuclear Energy, 2009Abstract The ATWS transient “Loss of main feed water supply” in a generic four-loop PWR at the nominal power of 3750 MW was analyzed using the coupled code system DYN3D/ATHLET. A variation of the MOX-fuel-assembly portion in the core has an effect on the reactivity coefficients of the fuel temperature and the moderator density.
Kliem, S. +3 more
openaire +2 more sources