Verification of the Code DYN3D/R with the Help of International Benchmarks
, 1997 Different benchmarks for reactors with quadratic fuel assemblies were calculated with the code DYN3D/R. In this report comparisons with the results of the reference solutions are carried out. The results of DYN3D/R and the reference calculation for the eigenvalue keff and the power distribution are shown for the steady-state 3-dimensional IAEA ...
Grundmann, U., Rohde, U.
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A Literature Survey of Neutronics and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters; Artificial Neural Networks as the VVER-1000 Core Predictor [PDF]
, 2011 Farshad Faghihi H. Khalafi +1 more
core +1 more source
Validation of coupled neutronic/thermal-hydraulic codes for VVER reactors - final report - FIKS-CT-2001-00166 [PDF]
, 2004 et, al +5 more
core +1 more source
KIT multi-physics developments for reactor analysis [PDF]
, 2017 Sanchez Espinoza, Victor Hugo
core +2 more sources
Annual Report 2003 - Institute of Safety Research [PDF]
, 2004 Rindelhardt, U., Weiß, F.-P.
core +1 more source
Annual Report 2008 - Institute of Safety Research [PDF]
, 2009 Rindelhardt, U., Weiß, F. P.
core +1 more source
The H2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors [PDF]
Sanchez-Espinoza, V. H.
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KIT results for the nodal based scenarios using DYN3D-COBRA-TF
, 2015 Jimenez, J., Sanchez, V.
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Development and verification of a transport solver for DYN3D
, 2014 Litskevich, D., Merk, B.
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Development of transport solutions for DYN3D. Current status.
, 2013 Litskevich, D., Merk, B.
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