Steam generator tube rupture risk impact on post-accident monitoring of French three-loop plants

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6496682

Zilliox, C

Experience with steam generator tube leak incidents in pressurized water reactor plants has resulted in an increase in Electricite de France's (EdF's) efforts at analysis and development of improvements in steam generator tube rupture accident treatment, taking into account single and multiple tube rupture with or without a steam break. This paper presents the analysis that leads to an evolution in post-accident monitoring for French three-loop 900-MW plants. The EdF approach can be summarized as follows: (1) a steam generator tube rupture consists of a second and third barrier simultaneously failing, resulting in radiological releases of reactor coolant system (RCS) fluid; (2) automatic and safety devices designed to cope with loss-of-coolant accidents (LOCAs) are able to maintain cladding and core integrity; (3) to recover third barrier integrity and to stop the leak, manual intervention is necessary; (4) if initial primary activity is low (according to stringent operating specifications) and remains low during the transient (according to emergency procedures relying on core safety priority), radiological consequences are low.

• Research Organization: Electricite de France, Villeurbanne
• OSTI ID: 6496682
• Report Number(s): CONF-860610-; TRN: 87-021587
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
RISK ASSESSMENT
STEAM GENERATORS
TUBES
RUPTURES
A CODES
C CODES
EMERGENCY PLANS
FAILURES
FISSION PRODUCT RELEASE
FRANCE
HEAT TRANSFER
MODIFICATIONS
REACTOR ACCIDENTS
SPECIFICATIONS
TRANSIENTS
TWO-PHASE FLOW
ACCIDENTS
BOILERS
COMPUTER CODES
ENERGY TRANSFER
EUROPE
FLUID FLOW
REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled