Dr.-Ing. Christoph Schuster

Key Activities

Teaching:

• Course „Basics of nuclear energy technology“ 
• Lecture „Transient performance of nuclear energy plants“ 
• Lecture „Nuclear and thermo hydraulic design of nuclear reactors“ 
• Work Placement „Transient performance of nuclear energy plants“

Research:

• Analysis of thermo hydraulic features of mono- and bi-phase natural circulation
• Security analysis of boiling water reactors

Scientific Biography

Publications

The public profile of Dr. Schuster can be found in the Research portal of the TU Dresden.

35 Entries

2024

• Posttest Calculations of Thermal-Hydraulic Conditions for Test Benches Simulating a Loss of Spent Fuel Pool Cooling Accident at BWR and VVER-1000/1200 ReactorsIvanova, N. V., Bedretdinov, M. M., Stepanov, O. E., Karetnikov, A. G., Moisin, D. N. & Schuster, C., May 2024, In:  Thermal engineering = Teploenergetika. 71, 5, p. 412-423, 12 p.Electronic (full-text) versionResearch output: Contribution to journal > Research article

2023

• Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditionsBedretdinov, M. M., Pantyushin, S. I., Stepanov, O. E., Melikhov, O. I. & Schuster, C., Jun 2023, In: Nuclear engineering and design. 407, 112271 p., 112271Electronic (full-text) versionResearch output: Contribution to journal > Research article

2022

• Safety cases for design-basis accidents in LWRs featuring passive systemsMull, T., Wagner, T., Bonfigli, G., Buchholz, S., Schäfer, F., Schleicher, E., Schuster, C. & 1 others, Feb 2022, In: Nuclear engineering and design. 387, 13 p., 111095Electronic (full-text) versionResearch output: Contribution to journal > Research article

2021

• KORSAR/GP and SOCRAT/V1 codes’ validation for the loss of cooling at spent fuel pool conditionsBedretdinov, M. M., Stepanov, O. E., Sledkov, R. M. & Schuster, C., 2 Aug 2021, In: Nuclear Engineering and Design. 2021, 375, 111089Electronic (full-text) versionResearch output: Contribution to journal > Research article
• Safety cases for design-basis accidents in LWRs featuring passive systems Part 2 – Numerical investigationsBonfigli, G., Buchholz, S., Schäfer, F., Kaczmarkiewicz, N., Schuster, C. & Sporn, M., Feb 2021, In: Nuclear engineering and design. 372, 110996Electronic (full-text) versionResearch output: Contribution to journal > Research article

2020

• Advanced natural circulation reduced-order model with inclined channel for low pressure conditionsManthey, R., Knospe, A., Lange, C., Schuster, C. & Hurtado, A., Apr 2020, In: Journal of nuclear engineering and radiation science. 6, 2, 21103Electronic (full-text) versionResearch output: Contribution to journal > Research article

2018

• Instrumentation for experiments on a fuel element mock-up for the study of thermal hydraulics for loss of cooling or coolant scenarios in spent fuel poolsArlit, M., Partmann, C., Schleicher, E., Schuster, C., Hurtado, A. & Hampel, U., Sep 2018, In: Nuclear Engineering and Design. 336, p. 105-111, 7 p.Electronic (full-text) versionResearch output: Contribution to journal > Research article
• Experimental investigation of the thermal hydraulics of a spent fuel pool under loss of active heat removal conditionsPartmann, C., Schuster, C. & Hurtado, A., 15 Apr 2018, In: Nuclear engineering and design. 330, p. 480-487, 8 p.Electronic (full-text) versionResearch output: Contribution to journal > Research article
• Advanced natural circulation reduced order model with inclined channel for low pressure conditionsManthey, R., Knospe, A., Lange, C., Schuster, C. & Hurtado, A., 2018, 2018 26th International Conference on Nuclear Engineering: Thermal-Hydraulics and Safety Analyses. The American Society of Mechanical Engineers(ASME), Vol. 6A. 8 p., V06AT08A021Electronic (full-text) versionResearch output: Contribution to book/conference proceedings/anthology/report > Conference contribution
• Thermal hydraulic analysis of the convective heat transfer of an air-cooled BWR spent fuel assemblyPartmann, C., Schuster, C. & Hurtado Gutierrez, A., 2018, In: ATW - Internationale Zeitschrift fur Kernenergie. 63, 6/7, p. 397-400Research output: Contribution to journal > Research article

This information is provided by the FIS.

Advanced natural circulation reduced order model with inclined channel for low pressure conditions
Manthey, R.; Knospe, A.; Lange, C.; Schuster, C.; Hurtado, A.:
ASME Journal of Nuclear Engineering and Radiation Science, 2019
Doi: 10.1115/1.4044846

Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools
P, Zedler, C. Schuster, W. Lippmann, A. Hurtado
Journal: Experimental and computational multiphase flow, 2019
DOI: 10.1007/s42757-019-0034-x

Effect of throttling on the two-phase flow stability in an open natural circulation system.
Manthey, R.; Schuster, C.; Lippmann, W.; Hurtado, A.
Heat and Mass Transfer, Springer, 2019,
doi: 10.1007/s00231-019-02679-x.

Experimental and theoretical investigation of the boiling heat transfer in a low-pressure natural circulation system
F. Viereckl, E. Schleicher, C. Schuster, W. Lippmann, A. Hurtado
Experimental and computational multiphase flow, 2019
https://doi.org/10.1007/s42757-019-0023-0

Experimental investigation of cross-overflow in spent fuel pools using the test facility ALADIN
P. Zedler, C. Schuster, W. Lippmann, A. Hurtado
Poster: KOMPOST-13th PhD student seminar;
2018 Zittau, Germany, December 13, 2018

Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools
P. Zedler, C. Schuster, W. Lippmann, A. Hurtado
Poster: 16th Multiphase Flow Conference
2018 Dresden, Germany, November 14-16, 2018

nvestigation of the condensation process on inclined tubes as part of passive heat transfer systems
Viereckl, F.; Schuster, C.; Hurtado A.:
Annual Meeting on Nuclear Technology, Hamburg, 10.-12. Mai 2016

Advanced Passive Cooling Solutions for Enhancement of Safety in Nuclear Power Plants
Reuter, M.; Ornot, L.; Schuster, C.; Hurtado, A.
36th Annual Conference of the Canadian Nuclear Society, Canada, Toronto 2016

Instrumentation for experiments on a fuel element mock-up for the study of thermal hydraulics for loss of cooling or coolant scenarios in spent fuel pools
Arlit, M.; Partmann, C.; Schleicher, E.; Schuster, C.; Hurtado, A.; Hampel, U.
SWINTH-2016; 15.-17. Juni 2016

Experimentelle Untersuchungen zur Nachwärmeabfuhr von Brennelementen in ausdampfenden BE-Nasslagern
Partmann, C.; Schuster, C.; Hurtado, A.
Annual Meeting on Nuclear Technology; 10.-12. Mai 2016

Analysis of natural-circulation systems with nonlinear instabilities perspectively on application of bifurcation analysis
Manthey, R.; Schuster, C.; Lange, C.; Hurtado, A.
Annual Meeting on Nuclear Technology, Hamburg, 10.-12. Mai 2016

Experimental investigations of BWR fuel elements in spent fuel pools – improvements and adjustments
C. Partmann; C. Schuster; A. Hurtado
Annual Meeting on Nuclear Technology, Berlin, May 5-7, 2015

Two-phase flow phenomena along an adiabatic riser – an experimental study at the test facility GENEVA
T. Cloppenborg, C. Schuster, A. Hurtado
International Journal of Multiphase Flow, Vol 72, June 2015, pages 112 – 132

Experimental investigations at the GENEVA passive residual heat removal test facility
T. Cloppenborg; C. Schuster; A. Hurtado
atw, 6:357-363, 2014 (Parallelveröffentlichung)

Experimental investigations at the GENEVA passive residual heat removal test facility
T. Cloppenborg; C. Schuster; A. Hurtado
VGB PowerTech, 5:57-63, 2014

AMNT 2014: Key topic reactor operation, safety – Report part 2
K.-C. Fischer; T. Höhne; T. Hollands; C. Schuster; A. Traichel; H.-G. Willschütz; B. Wortmann
atw Vol. 59 (2014) Issue 12/December; pp. 701 – 708

Experimental results of investigations at the natural circulation test facility GENEVA
T. Cloppenborg; C. Schuster; C. Partmann;  A. Hurtado
Annual Meeting on Nuclear Technology 2014, Frankfurt a. M., 06.-08. Mai 2014, Tagungsbericht+Vortrag

Generic experimental investigations of thermohydraulic instabilities with void fraction measurement at natural circulation test facility GENEVA
T. Cloppenborg; C. Schuster; A. Hurtado
22nd ICONE, Prague, 07.-11. Juli 2014, Proceedings+ Präsentation

Section report Annual Meeting on Nuclear Technology 2013 – Part 4
K.-C. Fischer; B. Schubert; C. Schuster; W.Tietsch;  A. Traichel; H.-G. Willschütz
atw Vol 58 (2013) Issue 12/December; pp. 720 - 726

Investigations into natural circulation driven heat removal systems
T. Cloppenborg; C. Schuster; A. Hurtado; S. Leyer
Jahrestagung Kerntechnik 2013, Berlin, 14.-16. Mai 2013, Tagungsbericht

Experimental Investigation of a Boil-Off-Scenario in BWR Spent Fuel Pools
Steffen Schulz, Christoph Schuster, Antonio Hurtado
21th International Conference on Nuclear Engineering, ICONE 21, 2013 Chengdu / China

Untersuchung des Transports von Isoliermaterial durch SWR-Abstandshalter beim Übergang zur Zweiphasenströmung
C. Schuster; H. Ohlmeyer; G. Laczko; M. Ignaczak; A. Hurtado
Jahrestagung Kerntechnik 2011, Berlin, 17.-19. Mai 2011, Tagungsbericht

Experimentelle Untersuchung der Brennstabbelastung in einem ausdampfenden Behälter
S. Schulz; C. Schuster; A. Hurtado
Jahrestagung Kerntechnik 2011, Berlin, 17.-19. Mai 2011, Tagungsbericht

Experimentelle Untersuchung des Einflusses reaktorspezifischer Kühlmittelzusätze auf Siedevorgänge in Druckwasserreaktoren
R. Nakath; C. Schuster; A. Hurtado
Jahrestagung Kerntechnik 2011, Berlin, 17.-19. Mai 2011, Tagungsbericht

Die Relevanz der Borflüchtigkeit bei Langzeittransienten in einem mit Bor vergifteten Siedewasserreaktor
S. Böhlke; H. Ohlmeyer; C. Schuster; A. Hurtado
Jahrestagung Kerntechnik 2009, 12.-14- Mai 2009, Dresden, Deutschland

About the volatility of boron in aqueous solutions of borates with vapour in relevance to BWR-Reactors
Böhlke S.; Schuster, C.; Hurtado, A.
International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”, 14-19.09.2008, Interlaken, Switzerland 

Experimentelle Untersuchung der Brennstabbelastung in einem ausdampfenden Brennelement-Lagerbecken
Schuster, C.; Ohlmeyer, H.
Jahrestagung Kerntechnik 2008, Tagungsbericht (Log Nr. 308), 27.–29.05.2008, Hamburg, Deutschland

Über die Flüchtigkeit von Boraten bei Siedewasserreaktoren
Böhlke S.; Ohlmeyer H.; Schuster C.; Hurtado A.
Jahrestagung Kerntechnik-2008, 27.–29.05.2008, Hamburg, Deutschland

Bestimmung des Borverlustes aus siedenden Boratlösungen bei Störfallbedingungen in Siedewasserreaktoranlagen
Böhlke, S.; Ohlmeyer, H.; Schuster, Ch.
Jahrestagung Kerntechnik 2007, Karlsruhe 22. – 24. Mai 2007, Tagungsbericht (CD)

Avoiding start-up instabilities in a two-phase natural circulation loop by an additional steam source
Schuster, C.; Knorr, J.
NURETH-11, October 2-6, 2005, Avignon, France, Proceedings Log No. 236

Analysis of experiments at the natural circulation loop DANTON with the code ATHLET
Schuster, C.; Knorr, J.
Jahrestagung Kerntechnik 2003, Berlin, 20. – 22. Mai 2003, Tagungsbericht S. 93 – 96

Simulation der thermohydraulischen Prozesse im Passiven Impulsgeber mit einem SIMULINK-Modell
Schuster, C.; Ringel, H.; Knorr, J.
Jahrestagung Kerntechnik 2001, Dresden, 15. - 17. Mai 2001, Tagungsbericht S. 87 - 90

Analysis of flow instabilities at the natural circulation loop DANTON with regard to non-linear effects
Schuster, C.; Ellinger, A.; Knorr, J.
Heat and Mass Transfer 36 (2000) 557-565, Springer-Verlag 2000

Flashing influenced two-phase flow at the natural circulation loop DANTON - Experimental investigations
Schuster, C.; Knorr, J.; Ringel, H.; Prasser, H.-M.; Zippe, W.
3rd European Thermal Sciences Conference, 10-13 September 2000, Heidelberg, Germany, Proceedings Vol 2, p. 1065 - 1070

Simulation of Parallel Risers in the Cooling-Air Cooler System of Siemens Model Vx4.3 Gas Turbines at the DANTON Test Facility
Knorr, J.; Schuster, C.; Gebke, K.; Weber, L.; Thiel, H.-J.
VGB PowerTech Vol. 80, 6/2000, p. 32 – 40

Simulation der parallelen Steigleitungen des Kühlluft-Kühler-Kreislaufs der Siemens-Gasturbinen Vx4.3 an der Versuchsanlage DANTON
Knorr, J.; Schuster, C.; Gebke, K.; Weber, L.; Thiel, H.-J.
VGB KraftwerksTechnik 80. Jg., 6/2000, S. 52 – 60

Investigation of the operation mode of Passive Pressure Pulse Transmitter
Ringel, H.; Schuster, C.; Knorr, J.
NURETH-9, San Francisco, California, October 3 - 8, 1999, Proceedings

Analysis of flow instabilities at the natural circulation loop DANTON with regard to non-linear effects
Schuster, C.; Ellinger, A.; Knorr, J.
EUROTHERM SEMINAR No. 63, 6-8 Sept. 1999, Genoa, Italy, Proceedings p. 117 - 126

Experimentelle Untersuchung der Aufteilung einer Zweiphasenströmung auf parallele Steigrohre an der Versuchsanlage DANTON
Schuster, C.; Knorr, J.
Jahrestagung Kerntechnik ´99, Karlsruhe, 18. - 20. Mai 1999, Tagungsbericht S. 87 – 90

Thermohydraulische Eigenschaften eines Passiven Impulsgebers
Ringel, H.; Schuster, C.; Knorr, J.
atw 43. Jg. (1998) Heft 12, S. 770 – 775

Untersuchung instationärer Prozesse beim Naturumlauf mit Zweiphasenströmung an der Versuchsanlage DANTON
Knorr, J.; Schuster, C.
Jahrestagung Kerntechnik `95, Nürnberg, 16. - 18. Mai 1995, Tagungsbericht S. 131 - 134