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Andreas Pautz
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Journal Articles

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.
Paper No: NERS-19-1059
https://doi.org/10.1115/1.4044910
Published Online: February 5, 2020
View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
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Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)
eBook Chapter

Design of Separated Element Reflector Experiments in CROCUS: PETALE

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
https://doi.org/10.1520/STP160820170090
ISBN: 978-0-8031-7661-4
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Proceedings Papers

Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code

Carlo Fiorina, Andreas Pautz, Konstantin Mikityuk
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81574
https://doi.org/10.1115/ICONE26-81574
View Paper titled, Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code
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Topics: Fuels, Physics, Computational fluid dynamics, Nuclear engineering, Nuclear fuels, Sodium fast reactors
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81082
https://doi.org/10.1115/ICONE26-81082
View Paper titled, Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor
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Topics: China, Construction, Cross section (Physics), Discrete element methods, Engineering simulation, Flow (Dynamics), Fuels, High temperature, Matlab, Nuclear fuel cycle
Proceedings Papers

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Stefan Radman, Carlo Fiorina, Konstantin Mikityuk, Andreas Pautz
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82260
https://doi.org/10.1115/ICONE26-82260
View Paper titled, A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors
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Topics: Sodium fast reactors, Physics, Modeling, Geometry, Neutrons, Simulation, Testing, Thermal hydraulics
Journal Articles

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiří Křepel, Konstantin Mikityuk, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011009.
Paper No: NERS-14-1038
https://doi.org/10.1115/1.4026401
Published Online: February 9, 2015
View Article titled, Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
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Topics: Equilibrium (Physics), Fuels, Graphite, Molten salt reactors, Neutrons, Nuclear fuel cycle, Design, Nuclear fission, Uranium
Proceedings Papers

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiři Křepel, Konstantin Mikityuk, Andreas Pautz
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A063, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31050
https://doi.org/10.1115/ICONE22-31050
View Paper titled, Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
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Topics: Graphite, Molten salt reactors, Cycles, Design, Equilibrium (Physics), Fuels, Optimization
Proceedings Papers

Molten Salt Fast Reactor Blanket Design and Proliferation Resistance Assessment

Valentyn Bykov, Jiři Křepel, Andreas Pautz
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A061, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31026
https://doi.org/10.1115/ICONE22-31026
View Paper titled, Molten Salt Fast Reactor Blanket Design and Proliferation Resistance Assessment
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Topics: Cycles, Design, Fast neutron reactors, Fluids, Hazards, Irradiation (Radiation exposure), Isotopes, Molten salt reactors, Neutron flux, Uranium
Proceedings Papers

Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

Jiři Křepel, Valentyn Bykov, Konstantin Mikityuk, Boris Hombourger, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30396
https://doi.org/10.1115/ICONE22-30396
View Paper titled, Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning
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Topics: Fuels, Molten salt reactors, Recycling, Cycles, Manufacturing, Matlab, Neutron flux, Neutrons, Nuclear fuel cycle, Safety
Proceedings Papers

Systematic Qualification of the Coupled Neutron Transport and Thermal-Hydraulics Code DORT-TD/THERMIX

Bismark Tyobeka, Andreas Pautz, Kostadin Ivanov
Proc. ASME. HTR2008, Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1, 511-520, September 28–October 1, 2008
Publisher: American Society of Mechanical Engineers
Paper No: HTR2008-58137
https://doi.org/10.1115/HTR2008-58137
View Paper titled, Systematic Qualification of the Coupled Neutron Transport and Thermal-Hydraulics Code DORT-TD/THERMIX
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Topics: Neutrons, Thermal hydraulics, Licensing, Nuclear design, Very high temperature reactors, Computers, Safety, Steady state, Transients (Dynamics)