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Reference accident (Core disruption accident - safety analysis detailed report no. 11)

Abstract

The PEC safety analysis led to the conclusion that all credible sequences (incident sequences characterized by a frequency of occurrence above 10/sup minus 7/ events per year) are limited to the design basis conditions of components of the plant protection systems, and that none of them leads to a release of mechanical energy or to an extensive damage of the core and primary containment structures event in the case of failure to scram. Nevertheless, as is done in other countries for similar reactors, some events beyond the limits of credibility were considered for the PEC reactor. These were defined on a absolutely hypothetical basis that involves severe core disruption and dynamic loading of primary containment boundary. A series of containments, each having a different role, was designed to mitigate the radiological effects of a postulated core disruptive accident. The final aim was to demonstrate that residual heat can be removed and that the release of radioactivity to the environment is within acceptable limits.
Authors:
Publication Date:
Jan 15, 1988
Product Type:
Conference
Report Number:
ETDE-IT-90-83; CONF-8801182-
Reference Number:
ITAN-90-002002; EDB-90-177760; ERA-16-000621
Resource Relation:
Conference: Workshop on the PEC reactor, Rome (Italy), 27-29 Jan 1988; Related Information: In: The PEC reactor. Safety analysis: Detailed reports, 217 p.
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PEC BRASIMONE REACTOR; REACTOR CORE DISRUPTION; AFTER-HEAT REMOVAL; CONTAINMENT SYSTEMS; DESIGN BASIS ACCIDENTS; ENVIRONMENTAL IMPACTS; MAXIMUM CREDIBLE ACCIDENT; RADIATION EFFECTS; RADIATION PROTECTION; REACTOR PROTECTION SYSTEMS; SAFETY STANDARDS; ACCIDENTS; BREEDER REACTORS; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL; STANDARDS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding; 220200 - Nuclear Reactor Technology- Components & Accessories; 220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
OSTI ID:
7871780
Research Organizations:
ENEA, Rome (Italy)
Country of Origin:
Italy
Language:
English
Other Identifying Numbers:
Other: ON: DE91725913
Submitting Site:
ITAN
Size:
p. 207-227
Announcement Date:
Mar 15, 2013

Citation Formats

Not Available. Reference accident (Core disruption accident - safety analysis detailed report no. 11). Italy: N. p., 1988. Web.
Not Available. Reference accident (Core disruption accident - safety analysis detailed report no. 11). Italy.
Not Available. 1988. "Reference accident (Core disruption accident - safety analysis detailed report no. 11)." Italy.
@misc{etde_7871780,
title = {Reference accident (Core disruption accident - safety analysis detailed report no. 11)}
author = {Not Available}
abstractNote = {The PEC safety analysis led to the conclusion that all credible sequences (incident sequences characterized by a frequency of occurrence above 10/sup minus 7/ events per year) are limited to the design basis conditions of components of the plant protection systems, and that none of them leads to a release of mechanical energy or to an extensive damage of the core and primary containment structures event in the case of failure to scram. Nevertheless, as is done in other countries for similar reactors, some events beyond the limits of credibility were considered for the PEC reactor. These were defined on a absolutely hypothetical basis that involves severe core disruption and dynamic loading of primary containment boundary. A series of containments, each having a different role, was designed to mitigate the radiological effects of a postulated core disruptive accident. The final aim was to demonstrate that residual heat can be removed and that the release of radioactivity to the environment is within acceptable limits.}
place = {Italy}
year = {1988}
month = {Jan}
}