Results 41 to 50 of about 647 (119)

Benchmarking of COBAYA3 pin-by-pin for VVER [PDF]

open access: yes, 2012
This paper presents results of the benchmarking of COBAYA3 pin-by-pin for VVER-1000 obtained in the frame of the EU NURISP project. The 3D lattice solver in COBAYA3 uses transport corrected multi-group diffusion approximation with side-dependent ...
Herrero Carrascosa, José Javier   +4 more
core  

Determination of volume of radioactive waste in activated VVER-1200 reactor structures

open access: yesВесці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук
The results of calculation studies of the amount of solid high-level, intermediate-level, low-level, very lowlevel radioactive waste (HLW, ILW, LLW, VLLW, respectively) generated during neutron activation of structural materials adjacent to the core of ...
M. L. Zhemzhurov   +6 more
doaj   +1 more source

DYN3D version 3.2 - code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements - description of models and methods - [PDF]

open access: yes, 2005
DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed.
Grundmann, Ulrich   +3 more
core   +1 more source

Validation of Pin Power Calculations Using DYN3D on MIDICORE Benchmark

open access: yesNuclear and Radiation Safety, 2019
Three-dimensional code DYN3D is widely used for the calculation of steady states and transients in light water reactors with hexagonal fuel assemblies like VVER. The capability of pin-by-pin power calculation is implemented in the code through an intranodal power reconstruction approach.
M. Ieremenko   +3 more
openaire   +2 more sources

Erzeugung und Nutzung von Bibliotheken von Zwei-Gruppen-Diffusionsparametern zur Berechnung eines KWU-Konvoi-Reaktors mit dem Reaktordynamik-Programm DYN3D [PDF]

open access: yes, 2002
Libraries of two-group neutron-diffusion parameters for a Siemens-KWU-Konvoi Pressurized Water Reactor have been generated at Forschungszentrum Rossendorf and TÜV Bau und Betrieb GmbH by using the codes HELIOS and CASMO, respectively.
Grundmann, Ulrich   +3 more
core   +1 more source

Development of CFD Thermal Hydraulics and Neutron Kinetics Coupling Methodologies for the Prediction of Local Safety Parameters for Light Water Reactors [PDF]

open access: yes, 2013
This dissertation contributes to the development of high-fidelity coupled neutron kinetic and thermal hydraulic simulation tools with high resolution of the spatial discretization of the involved domains for the analysis of Light Water Reactors transient
Peréz Mañes, Jorge
core   +2 more sources

Verifikation des 3-dimensionalen Kernmodells DYN3D/M2

open access: yes, 1994
Es wird eine Übersicht über die wesentlichsten Ergebnisse bisheriger Arbeiten zur Verifikation des dreidimensionalen Kernmodells DYN3D/M2 für Reaktoren mit hexagonalen Brennelementen gegeben. Verifikationsuntersuchungen für stationäre und instationäre Leistungsdichteberechnung, Thermohydraulik und Brennstabmodell sowie das Gesamtmodell werden ...
Grundmann, U., Rohde, U.
openaire   +2 more sources

Institute of Safety Research, Annual Report 1995 [PDF]

open access: yes, 1996
The report gives an overview on the scientific work of the Institute of Safety Research in ...
Rindelhardt, Udo, Weiß, Frank-Peter
core   +1 more source

Results of the application and demonstration calculations [PDF]

open access: yes, 2020
CORTEX - Research and Innovation Action (RIA) This project has received funding from the European Union's Horizon 2020 research and innovation programme under grant agreement No 754316.Publisher ...
Alexandridis, Georgios   +29 more
core  

The Code DYN3D/M2 for the Calculation of Reactivity Initiated Transients in Light Water Reactors with Hexagonal Fuel Elements -Code Manual and Input Data Description- [PDF]

open access: yes, 1993
The code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reactors with hexagonal fuel elements. The 3-dimensional neutron kinetics model HEXDYN3D of the code is based on a nodal expansion method for solving the two ...
Grundmann, Ulrich, Rohde, Ulrich
core   +1 more source

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