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Safety analysis of a loss-of-coolant accident in a breeding blanket for experimental fusion reactors

Conference · · Fusion Technol.; (United States)
OSTI ID:5788745
; ; ; ; ; ;
A LOCA in a blanket design proposed for NET (Next European Torus) is investigated. The structural analysis of a damaged breeder unit shows that this first containment barrier has a high probability of survival to this accident. The radioactive sources involved are evaluated and an assessment is made of all containment barriers and associated protection systems.
Research Organization:
Commission of the European Communities, Joint Research Centre, Ispra Establishment, Ispra (Va)
OSTI ID:
5788745
Report Number(s):
CONF-850310-
Conference Information:
Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCIDENTS
BREEDING BLANKETS
CONTAINMENT
CONTAINMENT SYSTEMS
DAMAGE
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
RADIATION EFFECTS
RADIATION PROTECTION
RADIATION SOURCES
REACTOR ACCIDENTS
REACTOR COMPONENTS
SYSTEMS ANALYSIS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS