Hochschulschrift
Development of advanced methods for safety assessment of sodium cooled fast reactors
- Location
-
Deutsche Nationalbibliothek Frankfurt am Main
- Extent
-
Online-Ressource
- Language
-
Englisch
- Notes
-
Dresden, Technische Universität Dresden, Dissertation, 2021
- Keyword
-
Sodium
Fast reactors
Evaluation
- Event
-
Veröffentlichung
- (where)
-
Dresden
- (who)
-
Technische Universität Dresden
- (when)
-
2022
- Creator
- Contributor
- URN
-
urn:nbn:de:bsz:14-qucosa2-787932
- Rights
-
Der Zugriff auf das Objekt ist unbeschränkt möglich.
- Last update
-
25.03.2025, 1:51 PM CET
Data provider
This object is provided by:
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Object type
- Hochschulschrift
Associated
- Bousquet, Jeremy
- Weiß, F. -. P.
- Hampel, Uwe
- Macian-Juan, R.
- Technische Universität Dresden
Time of origin
- 2022
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An advanced three-dimensional simulation system for safety analysis of gas cooled reactors
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Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors
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Development of advanced methods for safety assessment of sodium cooled fast reactors
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Physics investigations of sodium cooled fast reactors SNEAK-assembly 9A [nine-A]
Physics investigations of sodium-cooled fast reactors, SNEAK-Assembly 9C [nine C]
An advanced three-dimensional simulation system for safety analysis of gas cooled reactors
Physics investigations of sodium cooled fast reactors SNEAK-assemblies 6A/6B [six A, six B]
Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors
BNES-International Conference on Optimisation of Sodium-Cooled Fast Reactors vom 28.11.-01.12.1977 in London/England
Gas Cooled Reactors (HTGR, GCFBR)
Review of fuel failures in water cooled reactors
Physics investigations of sodium cooled fast reactors core Z 1 [one] MASURCA in SNEAK-assembly 6 [six] D
Element of nuclear safety : Research reactors
Development of advanced methods for safety assessment of sodium cooled fast reactors
Physics investigations of sodium-cooled fast reactors SNEAK-assembly 2 [two]
Physics investigations of sodium cooled fast reactors SNEAK-assembly 9A [nine-A]
Physics investigations of sodium-cooled fast reactors, SNEAK-Assembly 9C [nine C]
An advanced three-dimensional simulation system for safety analysis of gas cooled reactors
Physics investigations of sodium cooled fast reactors SNEAK-assemblies 6A/6B [six A, six B]
Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors
BNES-International Conference on Optimisation of Sodium-Cooled Fast Reactors vom 28.11.-01.12.1977 in London/England
Gas Cooled Reactors (HTGR, GCFBR)
Review of fuel failures in water cooled reactors
Physics investigations of sodium cooled fast reactors core Z 1 [one] MASURCA in SNEAK-assembly 6 [six] D