Published 1976
| Version v1
Report
Open
Operating control systems in advanced types of nuclear power plants
Description
The report presented first gives a general description of operating control of the PHENIX reactor, covering the level of automaticity and the methods of data perception. The authors then describe the control of the core, the supervision of cooling and the detection of cladding rupture. A summary description is given of the evolution of the SUPER-PHENIX reactor from its PHENIX predecessor. As regards high temperature reactors, the report discusses control rods, the regulation of the flow of coolant gas, the system of emergency stoppage and the general systems for safety and output limitation, with special attention being paid to particular aspects of some of the control systems
Availability note (English)
MF available from INIS under the Report Number.Files
7269039.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR; HTGR
Publishing Information
- Imprint Pagination
- 29 p.
- Report number
- ANL-Trans--1050
Conference
- Title
- Congress of the Society of Electrical, Electronic and Radio Engineers meeting.
- Dates
- 11 Sep 1973.
- Place
- Vittel, France.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7269039
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HTGR TYPE REACTORS; PHENIX REACTOR; REACTOR CONTROL SYSTEMS; SPECIFICATIONS
- Descriptors DEC
- BREEDER REACTORS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- Translation of French report CONF-730983--35.