Dr.-Ing. Christoph Schuster

Head of the research area “thermo hydraulics”

Mr Dr.-Ing. Christoph Schuster

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Institute of Process Engineering and Enviromental Technology - Chair of Hydrogen and Nuclear Energy

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Visiting address:

Walther-Pauer-Bau, PAU 218 George-Bähr-Straße 3b

01069 Dresden

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fax Fax: +49 351 463-37161

Key Activities

Teaching

Organisation of teaching at the WKET Chair
Course „Basics of nuclear energy technology“ for full-time and distance learning students
Lecture „Thermohydraulics of Nuclear Reactors“
Lecture „Nuclear safety methods“
Lecture „Transient power output of nuclear power plants“ as part of the lecture series ‘Environmental aspects of energy plants’

Research

Head of the ‘Thermohydraulics’ working group (2008 to 2020) with the following topics

Analysis of thermo hydraulic features of mono- and bi-phase natural circulation
Safety analyses of pressurised water reactors and boiling water reactors
Investigations into the effectiveness of passive safety systems
Investigations into the safety of fuel element storage pools

Scientific Biography

since 1992	Research Associate, Technische Universität Dresden, Chair of Hydorgen and Nuclear Energy
1992	PhD Thesis, Topic: “Research on Loop Operating Behaviour with Mono- and Bi-phase Natural Circulation
1987 - 1992	Scientific Assistant, Technische Universität Dresden, Chair of Nuclear Energy Technology
1982 - 1987	Studies of Energy System Technology, Technische Universität Dresden

Publications

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

36 Entries

2025

Spent fuel pool boil-off experiments with high power and high time resolutionSchuster, C. & Stepanov, O. E., Apr 2025, In: Nuclear engineering and design. 435, 113958Electronic (full-text) versionResearch output: Contribution to journal > Research article

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. 375, 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