Published January 1973
| Version v1
Report
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Control of the water-steam circuit of a nuclear power station
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes Mecaniques et Thermiques pour les Reacteurs a Neutron Rapides
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.Files
4077023.pdf
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(620.2 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- AAEC-LIB/Trans--497
INIS
- Country of Publication
- Australia
- Country of Input or Organization
- Australia
- INIS RN
- 4077023
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- GAS FLOW; HEAT EXCHANGERS; HTGR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; SAINT LAURENT-1 REACTOR; STEAM; STEAM GENERATORS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- BOILERS; CONTROL SYSTEMS; FLUID FLOW; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; NATURAL URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS
Optional Information
- Notes
- Translated from the French in Bull. Inf. Sci. Tech. (Paris) no. 167 p. 21-27 (1972) ) 7RN 029384{; bound with original. )]