Results 41 to 50 of about 94 (78)
Application of ATHLET/DYN3D/CTF to BWR TT without SCRAM
Perin, Yann +2 more
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Verification of the trigonal-geometry diffusion and SP3 models of the code DYN3D
Duerigen, S., Nikitin, E., Mittag, S.
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Entwicklung einer Version des Reaktordynamikcodes DYN3D für Hochtemperaturreaktoren
Rohde, U. +7 more
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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).
Soeren Kliem, Reuven Rachamin
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).
Soeren Kliem, Reuven Rachamin
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
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 ...
Emil Fridman, Reuven Rachamin
exaly +3 more sources
Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes
Annals of Nuclear Energy, 2019Abstract In this study, the isothermal physics tests performed on the fully loaded core of the Fast Flux Test Facility are analyzed with the Monte Carlo code Serpent and with the deterministic core simulator DYN3D. The selected tests comprise two neutron spectra measurements and a multitude of reactivity measurements (32 cases with control rod ...
Emil Fridman, Evgeny Nikitin
exaly +3 more sources
V1000CT-1 benchmark analyses with the DYN3D/RELAP5 and DYN3D/ATHLET coupled code systems
Kerntechnik, 2005Abstract 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. +4 more
+9 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
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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.
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