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

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

Part of:
Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 3

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

Optional Information