Published 1988
| Version v1
Book
Simulation of alternate recovery procedures and evaluation of operator error effects in case of a steam generator tube rupture transient
Creators
Description
The Steam Generator Tube Rupture (SGTR) occurred on June 25th 1979 at Doel-2 nuclear power plant (a 392 MWe pressurized water reactor with two loops), has been assumed as reference case for evaluating the potential effect of possible events or actions which might occur or could be taken during the transients. The events considered are related to operator errors or alternate recovery procedures and the results are evaluated in terms of the potential for radioactive releases and plant safety margins. Another aspect examined is the intrinsic plant behaviour in case of no operator action during the transient. The calculations are related to the first 2700 sec after the initiating event
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 3
- Imprint Pagination
- 340 p.
- Journal Page Range
- p. 1204-1213.
Conference
- Title
- International ENS/ANS Conference on thermal reactor safety.
- Dates
- 2-7 Oct 1988.
- Place
- Avignon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21068219
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DOEL-2 REACTOR; ERRORS; NUCLEAR OPERATORS; R CODES; RUPTURES; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS