Results 51 to 60 of about 94 (78)

The reactor dynamics code DYN3D – models, validation and applications

Progress in Nuclear Energy, 2016
Abstract 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.
Ulrich Rohde, Soeren Kliem, Ulrich Grundmann, Silvio Baier, Yuri Bilodid, Susan Duerigen, Emil Fridman, Andre Gommlich, Alexander Grahn, Lars Holt, Yaroslav Kozmenkov, Siegfried Mittag   +11 more
openaire   +2 more sources

DYN3D-MSR spatial dynamics code for molten salt reactors

Annals of Nuclear Energy, 2007
Abstract 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., Rohde, U., Grundmann, U., Weiß, F.-P.   +3 more
openaire   +2 more sources

The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D

Kerntechnik, 2012
Abstract DYN3D is a three-dimensional nodal code for steady-state and transient analyses of Light Water Reactors applicable for square and hexagonal fuel assembly geometries. Several versions of the DYN3D code are available including a multigroup diffusion and a simplified P3 (SP3) neutron transport option.
Duerigen, S., Fridman, E.
openaire   +3 more sources

Development of multi-physics code systems based on the reactor dynamics code DYN3D

Kerntechnik, 2011
Abstract The reactor dynamics code DYN3D has been coupled with the CFD code ANSYS CFX and the 3D thermal hydraulic core model FLICA4. In the coupling with ANSYS CFX, DYN3D calculates the neutron kinetics and the fuel behavior including the heat transfer to the coolant.
Kliem, S., Gommlich, A., Grahn, A., Rohde, U., Schütze, J., Frank, T., Gomez, A., Sanchez, V.   +7 more
openaire   +3 more sources

Ants and DYN3D Solutions to the IAEA-Hex Kinetics Benchmark

Nuclear Science and Engineering
A recently published two-dimensional, two-group hexagonal geometry IAEA-Hex kinetics benchmark was solved using the nodal neutronics programs Ants and DYN3D. Solutions to both the ramp and step transients were obtained with both programs. With Ants, the benchmark was solved using either the hexagonal geometry model or the triangular geometry model with
Rintala, A., Bilodid, Y.
openaire   +2 more sources

The modeling of fuel rod behaviour under RIA conditions in the code DYN3D

Fuel and Energy Abstracts, 2001
Abstract A description of the fuel rod behaviour and heat transfer model used in the code DYN3D for nuclear reactor core dynamic simulations is given. Besides the solution of heat conduction equations in fuel and cladding, the model comprises a detailed description of heat transfer in the gas gap by conduction, radiation and fuel-cladding contact ...
openaire   +4 more sources

Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation

Annals of Nuclear Energy, 2023
Soeren Kliem, Emil Fridman, Evgeny Nikitin   +2 more
exaly  

Integration of DYN3D inside the NURESIM Platform

2010
Gomez Torres, A. M., Sanchez Espinoza, V. H., Kliem, S., Gommlich, a., Rohde, U.   +4 more
openaire   +2 more sources

Spectral-history modeling in DYN3D burnup calculations

2008
Bilodid, Y., Mittag, S.
openaire   +3 more sources

Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D

Annals of Nuclear Energy, 2015
U Rohde, R Macian-Juan
exaly