DANGER CONTAINED IN A STEAM-COOLED FAST BREEDER REACTOR AND THE DOSE VALUE RELEASED TO THE ENVIRONMENT IN A SEVERE ACCIDENT; Die in einem damfgekuehlten schnellen Brut-reaktor enthaltene Gefaehrdung und die bei einem schweren Unfall in der Umgebung auftretenden Dosiswerte (in German)
Technical Report
·
OSTI ID:4070265
The requirements to be met by the containment system of the 1000 MW(e) steam cooled fast breeder reactor D 1 (KFK-392, Kernforschungszentrum Karlsruhe) are analyzed using the method proposed by Blaesser and Wirtz. For this purpose, the 'quantity of danger' of the predominant fission products for the nuclear fuel contained in the reactor core is calculated. By use of 'ouflow factors' the 'effective danger outflow' is obtained for the maximum credible accident. Taking into account a 'meterorological propagation factor' this yields directly the dose values. It is shown that a double containment is required for the respective plant to achieve sufficiently low dose values. (auth)
- Research Organization:
- Kernforschungszentrum, Karlsruhe (West Germany). Institut fuer Reaktorentwicklung
- NSA Number:
- NSA-25-028738
- OSTI ID:
- 4070265
- Report Number(s):
- NP-18781
- Country of Publication:
- Germany
- Language:
- German
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OSTI ID:4070265
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OSTI ID:4070265
Related Subjects
N38180* -Power Reactor Development-Safety & Siting
BREEDER REACTORS
CONTAINMENT
DESIGN
FAST REACTORS
FISSION PRODUCTS
MCA
RADIATION DOSES
SCFR
STEAM COOLANT
REACTORS
BREEDER/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)
REACTOR CONTAINMENT SYSTEMS/design for 1000 MW(e) steam cooled fast breeder
effects of maximum credible accident on
(T)
REACTORS
SUPERHEATING/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)
REACTORS
FAST/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)
BREEDER REACTORS
CONTAINMENT
DESIGN
FAST REACTORS
FISSION PRODUCTS
MCA
RADIATION DOSES
SCFR
STEAM COOLANT
REACTORS
BREEDER/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)
REACTOR CONTAINMENT SYSTEMS/design for 1000 MW(e) steam cooled fast breeder
effects of maximum credible accident on
(T)
REACTORS
SUPERHEATING/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)
REACTORS
FAST/containment system design for 1000 MW(e) steam cooled
effects of maximum credible accident on
(T)