Publications
Recent publications and conference contributions on ATHLET (selection)
2024
Vincenzo Anthony Di Nora, Philipp Schöffel
A New Gap Conductance Model for the ATHLET System Code
14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Operation and Safety (NUTHOS-14),, Vancouver, Canada, 2024
A. Papukchiev
Coupling of Computational Fluid Dynamics Codes with Structural Mechanics and System Thermal-Hydraulics Programs and Their Validation on Nuclear Reactor Relevant Experiments
BgNS TRANSACTIONS volume 26 number 1 (2022/23) pp. 57–66, 2024
Z. Yang, J. Herb, A. Papukchiev
Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment
Kerntechnik, 2024. https://doi.org/10.1515/kern-2023-0137
J. Herb, F. Weyermann
Implementation of the preCICE coupling interface for AC2/ATHLET
Kerntechnik, 2024. https://doi.org/10.1515/kern-2023-0119
2023
L. Guo, T. Hollands, H. Austregesilo
Validation on SBLOCA Experiment of the ACME Test Facility using the ATHLET code
NURETH-20, August 20 -25, 2023, Washington DC, USA
L. Guo, A. Seubert, P. Schöffel
Numerical Evaluation of the Thermal-hydraulic Effect due to the Thermal Expansion Behavior of Fuel Sabassembly
NURETH-20, August 20 -25, 2023, Washington DC, USA
S. Buchholz
AC2-ATHLET Simulations of PERSEO Test Facility
NURETH-20, August 20 -25, 2023, Washington DC, USA
A. Berezhnyi *, A. Krushynskyi, D. Ruban, S. Sholomitsky
Conservative evaluation of radionuclides release for VVER-440 and
VVER-1000 type reactors
Annals of Nuclear Energy 194, 2023
V. A. di Nora, T. Hollands, A. Wielenberg
Implementation and Application of a GitLab Continuous Integration Pipeline for AC2 Validation
NENE, 32nd International Conference Nuclear Energy, Portoroz, Slovenien, September 11-14, 2023
2022
E. Diaz-Pescador, M. Jobst, S. Kliem,
NuScale SMR 3-D Modelling and Applied Safety Analyses with the System Code ATHLET in the Framework of the EU H2020 McSAFER
13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13), Taiwan, September 5-10, 2022
Markus Hofer, Frieder Hecker, Michael Buck, Jörg Starflinger,
Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO2 heat removal system coupled to a pressurized water reactor
EPJ Nuclear Sci. Technol. 8, 34 (2022), https://doi.org/10.1051/epjn/2022039
J. Lee, M. Junk, T. Skorek, P. Schöffel,
Improvement of entrainment model for horizontal flow in ATHLET and application to Mantilla experiment and TPTF
Nuclear Engineering and Design 400 (2022), https://doi.org/10.1016/j.nucengdes.2022.112066
E. Diaz-Pescador, F. Schäfer, S. Kliem,
On the validation of ATHLET 3-D features for the simulation of multidimensional flows in horizontal geometries under single-phase subcooled conditions
Nuclear Engineering and Technology, 2022, ISSN 1738-5733, https://doi.org/10.1016/j.net.2022.04.017.
Nelson Felipe Rincón Soto, Michael Buck, Jörg Starflinger,
ASSESSMENT AND VALIDATION OF ATHLET-CODE FOR SIMULATING PASSIVE RESIDUAL HEAT REMOVAL VIA LOOP THERMOSYPHONS IN SMALL MODULAR REACTORS,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
Jaejin Lee, Markus Junk, Tomasz Skorek, and Philipp Schöffel,
IMPROVEMENT OF ENTRAINMENT MODEL FOR HORIZONTAL FLOW IN ATHLET AND APPLICATION TO MANTILLA EXPERIMENT AND TPTF,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
T.Skorek,
TWO FLUID ANNULAR FLOW MODEL FOR ATHLET,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
S.Buchholz,
DEVELOPMENT AND VALIDATION OF ATHLET FOR COMPACT PLATE HEAT EXCHANGER,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
Julia Krieger, Christoph Bratfisch, Marco K. Koch,
SIMULATION OF HEAT TRANSFER IN HELICALLY COILED HEAT EXCHANGERS WITH THE SYSTEM CODE AC2 -ATHLET
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
T. Skorek, D. von der Cron , L. Guo, P. Schöffel,
THE THREE-FIELD MODEL IN THE CODE ATHLET,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
N. Dünne, T. Skorek, P. Schöffel,
SIMULATION OF THE OPEN TESTS OF OECD/NEA RBHT BENCHMARK WITH ATHLET,
Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), ISBN 9789076971261, Brussels, Belgium, March 06, 2022
A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr,
Superphenix Benchmark Part II: Transient Results,
Journal of Nuclear Engineering and Radiation Science, Vol. 8, January 2022
Markus Hofer, Haikun Ren, Frieder Hecker, Michael Buck, Dieter Brillert, Jörg Starflinger,
Simulation, analysis and control of a self-propelling heat removal system using supercritical CO2 under varying boundary conditions,
Energy, Volume 247, 2022, https://doi.org/10.1016/j.energy.2022.123500.
V. Martinez-Quiroga, M. Szogradi, S. Schollenberger, M. Sanchez-Perea, N. Sandberg, J. Zhongyun, P. Freydier, M. Suslov, H. Austregesilo, T. Glantz, J.H. Lee, Z. Li, I. Shvetsov, R. Mukin, J. Holmstrom, J.F. Villanueva, E. Virtanen, J. Freixa,
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment,
Nuclear Engineering and Design, Volume 389, 2022, 111632, ISSN 0029-5493,
https://doi.org/10.1016/j.nucengdes.2021.111632
Jaejin Lee, Tomasz Skorek, Markus Junk, Philipp Josef Schöffel: Improved correlation of liquid entrainment fraction in horizontal pipes,
Nuclear Engineering and Design, Volume 388, 2022, 111615, ISSN 0029-5493,
https://doi.org/10.1016/j.nucengdes.2021.111615
2021
Angel Papukchiev, Zhi Yang: Application of the coupled code ATHLET-ANSYS CFX for the simulation of the flow mixing inside the ROCOM test facility,
Progress in Nuclear Energy, Volume 137, 2021
E. Diaz Pescador, F. Schäfer, S. Kliem: Modelling of multidimensional effects in thermal-hydraulic system codes under asymmetric flow conditions – Simulation of ROCOM Tests 1.1 and 2.1 with ATHLET 3D-Module
Nuclear Engineering and Technology, In Press, Available online 24 April 2021
2020
K.Kosovski, M. Seidl: External Hazard Coinciding With Small Break LOCA - Thermohydraulic Calculation With System Code ATHLET
Journal of Nuclear Engineering and Radiation Science, Vol.6, April 2020
2019
Chong Shen et al.: Transient safety anaysis of M²LFR-1000 reactor using ATHLET
Nuclear Engineering and Technology 51, 116-124, 2019
E. Diaz Pescador, F. Schäfer, S. Kliem: Thermal-hydraulic insights during a main steam line break in a generic PWR KONVOI reactor with ATHLET 3.1A
Kerntechnik 84/5, October 2019
M. Hofer, M. Buck, J. Starflinger: ATHLET extensions for the simulation of supercritical carbon dioxide driven power cycles
Kerntechnik 84/5, October 2019
T. Gschnaidtner, I. Aymerich Rodrigáñez, G. Lerchl, C. Wieland, H. Spliethoff: Heat transfer to water near the critical point: evaluation of the ATHLET thermal-hydraulic system code
Kerntechnik 84/5, October 2019
F. Weyermann: Development of AC² for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs
Kerntechnik 84/5, October 2019
T. Hollands, S. Buchholz, A. Wielenberg: Validation of the AC² Codes ATHLET and ATHLET-CD
Kerntechnik 84/5, October 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
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, USA, August 18-23, 2019
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,
Nuclear Engineering and Design Volume 354, December 2019,
https://doi.org/10.1016/j.nucengdes.2019.110211
T. Skorek et al: Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark,
Nuclear Engineering and Design Volume 354, 1 December 2019
https://doi.org/10.1016/j.nucengdes.2019.110199
J. Herb: How-to keep legacy simulation codes alive and continue developing them: A continuous integration process for a nuclear safety analysis code system. Presentation, Continuous Lifecycle: London, 2019.
2018
S. Buchholz et al.: EASY – Evidence of Design Basis Accidents Mitigation Solely with Passive Safety Systems
12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018
A. Schaffrath et al.: The nuclear simulation chain of GRS and its improvements for new ALWR and SMR typical phenomena
12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018
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,
https://www.sciencedirect.com/science/article/pii/S0306454918302056#!
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
Journal of Nuclear Technology, Volume 203, 2018
2017
H. Austregesilo and T. Hollands: Contibution of the OECD ATLAS Project to the Assessment of the Thermal-Hydraulic System Code ATHLET
NURETH-17: The17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi'an, Shaanxi, China, Sept. 3-8, 2017
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
NURETH-17: The17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi'an, Shaanxi, China, Sept. 3-8, 2017
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
NURETH-17: The17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi'an, Shaanxi, China, Sept. 3-8, 2017
C. Ceuca et al.: CFD and System Analysis Code Investigations of the Multidimensional Flow Mixing Phenomena in the Reactor Pressure Vessel
Proceedings of ICAPP 2017, Fukui and Kyoto (Japan), April 24-28, 2017
B.Batki et al.: Analyses of unprotected transients in GFR (ALLEGRO) and SFR reactors supporting the group constant generation methodology
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russia, 26-29 June 2017
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
Gyeongju, Korea, October 9-13, 2016
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
NURETH-16: The16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, USA, Aug 30-Sept 4, 2015
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
Master Thesis, Technische Universität München, 2017
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
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