Physics investigations of sodium cooled fast reactors core Z 1 [one] MASURCA in SNEAK-assembly 6 [six] D
- Location
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Deutsche Nationalbibliothek Frankfurt am Main
- Dimensions
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30 cm
- Extent
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54, [36] S.
- Language
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Deutsch
- Notes
-
35 graph. Darst.;
- Event
-
Veröffentlichung
- (where)
-
Cadarache
- (who)
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Centre d'Etudes Nucléaires
- (when)
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1972
- Event
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Veröffentlichung
- (where)
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Karlsruhe
- (who)
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Ges. f. Kernforschung mbH
- (when)
-
1972
- Creator
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Hammer, Philippe
Plum, Fritz
- Table of contents
- Rights
-
Bei diesem Objekt liegt nur das Inhaltsverzeichnis digital vor. Der Zugriff darauf ist unbeschränkt möglich.
- Last update
-
11.06.2025, 2:02 PM CEST
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.
Associated
- Hammer, Philippe
- Plum, Fritz
- Centre d'Etudes Nucléaires
- Ges. f. Kernforschung mbH
Time of origin
- 1972
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Gas Cooled Reactors (HTGR, GCFBR)
Development of advanced methods for safety assessment of sodium cooled fast reactors
Development of advanced methods for safety assessment of sodium cooled fast reactors
The high-temperature gas-cooled and advanced gas-cooled reactors : Literature survey
Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors
Review of fuel failures in water cooled reactors
BNES-International Conference on Optimisation of Sodium-Cooled Fast Reactors vom 28.11.-01.12.1977 in London/England
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]
Physics investigations of sodium cooled fast reactors SNEAK-assemblies 6A/6B [six A, six B]
Physics investigations of sodium cooled fast reactors SNEAK-assembly 9 [nine] B, P. 1. / With contributions from E. A. Fischer [u. a.]
Gas Cooled Reactors (HTGR, GCFBR)
Development of advanced methods for safety assessment of sodium cooled fast reactors
Development of advanced methods for safety assessment of sodium cooled fast reactors
The high-temperature gas-cooled and advanced gas-cooled reactors : Literature survey
Numerical Simulation of Fluid-Structure Interaction during the Expansion Phase in Sodium Cooled Fast Reactors
Review of fuel failures in water cooled reactors