Reliability of reactor pressure components : proceedings of an Internat. Symposium on Reliability of Reactor Pressure Components held in Stuttgart, 21 - 25 March 1983
- Location
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Deutsche Nationalbibliothek Frankfurt am Main
- ISBN
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9200508839
- Dimensions
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24 cm
- Extent
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415 S.
- Notes
-
Ill., graph. Darst.
Literaturangaben
- Keyword
-
Technische Zuverlässigkeit
Reaktorwerkstoff
Bruchmechanik
Rissbildung
Primärkühlkreis
Zuverlässigkeit
Kernreaktorwerkstoff
Bruchmechanik
Rissbildung
Primärkühlkreislauf
- Event
-
Veröffentlichung
- (where)
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Vienna
- (who)
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IAEA
- (when)
-
1983
- Contributor
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Internationale Atomenergie-Organisation
International Symposium on Reliability of Reactor Pressure Components (1983 : Stuttgart)
- Table of contents
- Rights
-
Bei diesem Objekt liegt nur das Inhaltsverzeichnis digital vor. Der Zugriff darauf ist unbeschränkt möglich.
- Last update
-
11.06.2025, 2:04 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
- Internationale Atomenergie-Organisation
- International Symposium on Reliability of Reactor Pressure Components (1983 : Stuttgart)
- IAEA
Time of origin
- 1983
Other Objects (12)
IAEA International Symposium on Reliability of Reactor Pressure Components vom 21.-25. März 1983 in Stuttgart
International Atomic Energy Agency (IAEA): International Symposium on Reliability of Reactor Pressure Components in Stuttgart vom 21.-25.3.1983
Trino Reactor Pressure Vessel
Reliability of digital reactor protection system based on extenics
Importance Index of Components in Uncertain Reliability Systems
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Device for Relieving Pressure in a Reactor
High‐Pressure Reactor Technology for Aerated Biotransformations
High-pressure reactor technology for aerated biotransformations
THEDRA, a code for thermal design reliability analysis of a reactor core
Reliability of optical fibres and components : final report of COST 246
IAEA International Symposium on Reliability of Reactor Pressure Components vom 21.-25. März 1983 in Stuttgart
International Atomic Energy Agency (IAEA): International Symposium on Reliability of Reactor Pressure Components in Stuttgart vom 21.-25.3.1983
Trino Reactor Pressure Vessel
Reliability of digital reactor protection system based on extenics
Importance Index of Components in Uncertain Reliability Systems
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Device for Relieving Pressure in a Reactor
High‐Pressure Reactor Technology for Aerated Biotransformations
High-pressure reactor technology for aerated biotransformations
THEDRA, a code for thermal design reliability analysis of a reactor core
Reliability of optical fibres and components : final report of COST 246
IAEA International Symposium on Reliability of Reactor Pressure Components vom 21.-25. März 1983 in Stuttgart
International Atomic Energy Agency (IAEA): International Symposium on Reliability of Reactor Pressure Components in Stuttgart vom 21.-25.3.1983
Trino Reactor Pressure Vessel
Reliability of digital reactor protection system based on extenics
Importance Index of Components in Uncertain Reliability Systems
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components under Transient Light Water Reactor Operating Conditions (CASTOC)
Device for Relieving Pressure in a Reactor
High‐Pressure Reactor Technology for Aerated Biotransformations
High-pressure reactor technology for aerated biotransformations
THEDRA, a code for thermal design reliability analysis of a reactor core