Publications
Publications and conference contributions
2019
Y. Périn, R. Henry, K. Velkov and S. P. Nikonov: Transient Analysis of a Detailed Thermal-Hydraulic Model of a VVER-1000 Core with the System Code ATHLET |
Wielenberg, L. Lovasz, P. Pandazis, A. Papukchiev, L. Tiborcz, P.J. Schöffel, C. Spengler, M. Sonnenkalb, A. Schaffrath: Recent improvements in the system code package AC2 2019 for the safety analysis of nuclear reactors, Skorek, T. et al: Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark, |
2018
S. Buchholz et al.: EASY – Evidence of Design Basis Accidents Mitigation Solely with Passive Safety Systems |
A. Schaffrath et al.: The nuclear simulation chain of GRS and its improvements for new ALWR and SMR typical phenomena |
| J. Herb: A Continuous Integration Platform for the Deterministic Safety Analysis Code System AC² Proceedings of the 2018 26th International Conference on Nuclear Engineering ICONE-26, July 22-26 2018, London, England |
B. Batki, A, Keresztúri, A., I. Panka: Calculation of core safety parameters and uncertainty analyses during unprotected transients for the ALLEGRO and a sodium-cooled fast reactor,Annals of Nuclear Energy, Volume 118, Issue undefined, August 2018 https://www.sciencedirect.com/science/article/pii/S0306454918302056#! |
B. Batki, A, Keresztúri, A., I. Panka: Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code, Kerntechnik, Volume 83, Issue 4, August 2018, |
J. Hádek and R. Meca:Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes, ÚJV Řež, a. s., Hlavní 130, 250 68 Husinec-Řež Czech Republic, Kernenergie Volume 83, Issue 4 (August 2018) https://www.hanser-elibrary.com/doi/10.3139/124.110902 |
A. Bousbia Salah, S. C. Ceuca et al.: Unsteady single phase natural circulation flow mixing prediction using 3D thermal-hydraulic system and CFD codes |
2017
H. Austregesilo and T. Hollands: Contibution of the OECD ATLAS Project to the Assessment of the Thermal-Hydraulic System Code ATHLET |
S. Buchholz, P. Schoeffel, A. Schaffrath: Exemplification of the AC² Multidimensional Capabilities to the Application of Large Pools within the Frame of the German EASY Project |
H. Hristo, J. Preuss, S. Buchholz, A. Schaffrath: Validation Work for the Containment Cooling Condenser with the Syste Code ATHLET within the Frame of the German EASY Project |
C. Ceuca et al.: CFD and System Analysis Code Investigations of the Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel |
B.Batki et al.: Analyses of unprotected transients in GFR (ALLEGRO) and SFR reactors supporting the group constant generation methodology |
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2016
L. Tiborcz and H. Austregesilo: Simulation of the ATLAS Benchmark Test A5.1 with the Code ATHLET NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety |
| T. Skorek and L. Tiborcz: Validation of ATHLET System Code Scaling Effects by Simulation of Reflooding Experiments NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety Gyeongju, Korea, October 9-13, 2016 |
| S. Buchholz, D. von der Cron and A. Schaffrath: System code improvements for modelling passive safety systems and their validation Kerntechnik 81 (2016) 5, Carl Hanser Verlag, München |
| S. C. Ceuca and D. Laurinavicius: Experimental and Numerical Investigations on the Direct Contact Condensation Phenomenon in Horizontal Flow Channels and its Implications in Nuclear Safety Kerntechnik 81 (2016) 5, Carl Hanser Verlag, München |
| A. Schaffrath et al.: Scientific codes developed and used at GRS - Nuclear simulation chain Kerntechnik 81/2 (2016) |
2015
| V. di Marcello et al.: Validation of the thermal-hydraulic system code ATHLET based on selected pressure drop and void fraction BFBT tests Nuclear Engineering and Design 288 (2015) 183–194 |
| Nikolay Khrennikov et al.: Application of 3-D coupled code QUABOX/CUBBOX-ATHLET for RBMK-1000 vapor reactivity coefficient measurements Annals of Nuclear Energy 84 (2015) 220–224 |
D. von der Cron, H.V. Hristov, A. Seubert: Modeling of the Thermal Hydraulics of Very-High-Temperature Reactors with the System Code ATHLET |
| P. Pandazis, S.C. Ceuca, P.J. Schoeffel and H.V. Hristov: Investigation of Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel with the System Code Athlet NURETH-16: The16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, USA, Aug 30-Sept 4, 2015 |
2014
| S. Ceuca et al.: Best-Estimate Simulations of Condensation-induced Water Hammer in Horizontal Pipes with the System Analysis Code ATHLET Multiphase Science and Technology, 26 (4): 305–327 (2014) |
| P.J. Schöffel, H.V. Hristov, G. Lerchl: Towards Multidimensional Thermalhydraulic Simulations with the System Code ATHLET 45th Annual Meeting on Nuclear Technology, Frankfurt, Germany, 2014 |
| A. Vojacek and G. Mazzini: Analyses of the Start-Up and Shut-Down of SCWR Fuel Qualification Test Loop. International Conference on Nuclear Engineering, Proceedings, ICONE. 2. . 10.1115/ICONE22-30673, 2014. |
PhD and Master Thesis
A. Iglesias Moreno: Implementation of an advanced numerical method for the optimization of the ATHLET-OpenFOAM coupling capabilities |
| K. Huber: A Multiscale Method for Mixed Convective Systems: Coupled Calculations with ATHLET and OpenFOAM of the PHENIX NCT PhD Thesis, Karlsruhe Institute of Technology, 2017 |
| V. Jacht: Verteile Parallelisierung thermohydraulischer Simulationen in ATHLET mihilfe von PETSc Master Arbeit, Fakultät für Informatik, Technische Universität München, 2017 |
| C. Lui: Numerical Simulation of Water Hammer with the System Analysis Code ATHLET Master Thesis, Technische Universität München, 2017 |
| S. Thaler: Vergleichsstudie zwischen den thermohydraulischen Simulationscodes ATHLET (GRS) & APROS (VTT) Bachelorarbeit, Lehrstuhl für Energiesysteme, Technische Universität München, 2016 |
| J. Venker: Development and Validation of Models for Simulation of Supercritical Carbon Dioxide Brayton Cycles and Application to Self-Propelling Heat Removal Systems in Boiling Water Reactors PhD Thesis, Institut für Kernenergetik und Energiesysteme, Universität Stuttgart, 2015 |
| C. Ceuca: Computational Simulations of Direct Contact Condensation as the Driving Force for Water Hammer PhD Thesis, Fakultät für Maschinenwesen, Technische Universität München, 2015 |
