Development of an integrated heat exchanger/steam generator IDA for sodium- cooled fast breeder reactors. Final report. Entwicklung eines integrierten waermetauschers/dampferzeugers IDA fuer natriumgekuehlte schnelle brueter. Schlussbericht (in German)
The object of this study was to find out whether a concept could be realized which would allow eliminating the intermediate system which is normally used for sodium cooled power reactors as the secondary sodium heat transfer system located between the radioactive primary sodium system and the water-steam system. First it was proved that this was technically possible by using a reaction-proof steam generator, called IDA, with a triple-wall-tube-steel-copper-steel as a heat exchanging element. The triple-wall-tube shall exclude damage arising from a direct contact between the radioactive reactor coolant sodium with the working medium water-steam. The main points of this research project were technical and metallurgical investigations regarding the operation and failure characteristics of the triple-wall-tube. The test of a MW-prototype steam generator as well as the thermodynamic and functional studies about an IDA - nuclear power station with the same safety requirements as the SNR-300 reference reactor were found to be satisfactory. Based on the results which are avaliable at present, the idea of a fast breeder power reactor with a primary sodium-heated reaction-proof steam-generator seems to be basically possible, and a continuation of the development programme aiming at a technically sound and economically interesting design is therefore considered to be a worthwhile policy. (auth)
- Research Organization:
- Bundesministerium Fuer Bildung Und Wissenschaft, Bonn (Germany); Internationale Atomreaktorbau GmbH, Bensberg/Koln (Germany)
- NSA Number:
- NSA-27-023904
- OSTI ID:
- 4556496
- Report Number(s):
- BMBW-FBK-72-28
- Country of Publication:
- Germany
- Language:
- German
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