Dr.-Ing. Christoph Schuster
Table of contents
Head of the research area “thermo hydraulics”
NameMr Dr.-Ing. Christoph Schuster
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Institute of Process Engineering and Enviromental Technology - Chair of Hydrogen and Nuclear Energy
Institute of Process Engineering and Enviromental Technology - Chair of Hydrogen and Nuclear Energy
Visiting address:
Walther-Pauer-Bau, PAU 218 George-Bähr-Straße 3b
01069 Dresden
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.
2018
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Thermal hydraulic analysis of the convective heat transfer of an air-cooled BWR spent fuel assembly , 2018, In: ATW - Internationale Zeitschrift fur Kernenergie. 63, 6/7, p. 397-400Research output: Contribution to journal > Research article
2017
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Convective heat transfer of an air cooled BWR spent fuel assembly , May 2017, 48th Annual Meeting on Nuclear TechnologyResearch output: Contribution to book/conference proceedings/anthology/report > Conference contribution
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Experimental investigation about the thermal hydraulics of evaporating spent fuel pools , 2017Research output: Book/Report/Anthology > Conference proceeding
2016
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Safety studies of decay heat removal from spent fuel in evaporating spent fuel pools , Oct 2016, Kraftwerkstechnisches KolloquiumResearch output: Contribution to book/conference proceedings/anthology/report > Conference contribution
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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 , Jun 2016, SWINTH-16Research output: Contribution to book/conference proceedings/anthology/report > Conference contribution
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Experimental studies on decay heat removal from spent fuel in evaporating spent fuel pools , May 2016, 47th Annual Meeting on Nuclear TechnologyResearch output: Contribution to book/conference proceedings/anthology/report > Conference contribution
2014
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Key topic reactor operation, safety – Report part 2 , 2014, In: ATW - Internationale Zeitschrift fur Kernenergie. 2014, 12, p. 701-708Research output: Contribution to journal > Research article
2013
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INVESTIGATIONS INTO NATURAL CIRCULATION DRIVEN HEAT REMOVAL SYSTEMS , 2013, Tagungsbericht Jahrestagung Kerntechnik 2013Research output: Contribution to book/conference proceedings/anthology/report > Conference contribution
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Section report Annual Meeting on Nuclear Technology 2013-Part 4 , 2013, In: ATW - Internationale Zeitschrift fur Kernenergie. 2013, 12, p. 720-726Research output: Contribution to journal > Research article
2009
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Die Relevanz der Borflüchtigkeit bei Langzeittransienten in einem mit Bor vergifteten Siedewasserreaktor , May 2009, Tagungsband der Jahrestagung Kerntechnik 2009. 311Research output: Contribution to book/conference proceedings/anthology/report > Conference contribution