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Fabregue, J.-P.; Lauret, Ph.; Mireau, J.-P.
Boiler dynamics and control in nuclear power stations 31986
Boiler dynamics and control in nuclear power stations 31986
AbstractAbstract
[en] For the Superphenix 1200 MWe fast breeder plant, high capacity steam generators (750 MWth) were designed and manufactured. For the Superphenix 2 1500 MWe breeder project, it is planned to use the same type of steam generators. For the thermal hydraulic analysis of these steam generators, a 1-D code, PGFAA, was used to study their steady state behaviour and static operating stability. The code was validated by comparison with test results obtained on a 45 MWth mockup at the EDF Les Renardieres test facilities. 1-D codes are also used to study steam generator behaviour with fast or high amplitude transients (VARESE for Superphenix 1, DYN1 and GVDEC for Superphenix 2). The main characteristics of these codes are described and a few examples given of transient calculation results. (author)
Primary Subject
Source
British Nuclear Energy Society, London; 342 p; ISBN 0 7277 0269 6;
; 1986; p. 267-273; British Nuclear Energy Society; London (UK); 3. international conference on boiler dynamics and control in nuclear power stations; Harrogate (UK); 21-25 Oct 1985; Price Pound65.00

Record Type
Book
Literature Type
Conference
Country of publication
BOILERS, BREEDER REACTORS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EVALUATION, FAST REACTORS, FBR TYPE REACTORS, FLUID MECHANICS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MECHANICS, PLUTONIUM REACTORS, REACTORS, SODIUM COOLED REACTORS, STRUCTURAL MODELS, VAPOR GENERATORS
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