Published 1970
| Version v1
Book
Performance of prestressed concrete reactor vessels of the French nuclear reactor program from Marcoule to Bugey I
Description
no abstract available
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- Imprint Title
- Performance of nuclear power reactor components
- Imprint Pagination
- p. 363-376.
- Series
- Proceedings series.
Conference
- Title
- Symposium on performance of nuclear power reactor components.
- Dates
- 10 Nov 1969.
- Place
- Prague, Czechoslovakia.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 1000411
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- RELIABILITY; PRESTRESSED CONCRETE; EDF-5; G-1; PRESSURE TUBES; THERMAL INSULATION; PRESSURE VESSELS; BOILERS; PUMPS; THERMAL STRESSES; FAILURES; COOLANT LOOPS; VIBRATIONS; FLOW MODELS; SHRINKAGE; THERMAL CONDUCTIVITY; FRICTION; CORROSION PROTECTION; BUCKLING; STAINLESS STEELS; HEAT EXCHANGERS; CABLES; RELAXATION
Optional Information
- Secondary number(s)
- IAEA-SM--127/17.