Abstract
The mechanical properties of structural materials of sodium cooled fast reactors have to be evaluated under the influence of the liquid metal environment. The liquid sodium coolant which is circulating through the primary system of a fast neutron reactor is of high purity. Its capacity to reduce passivating layers and to remove carbon from structural steel has to be considered. Thus, a programme to study the influence of very pure flowing sodium on the creep-rupture and fatigue properties of austenitic steels, AISI types 304 and 316L(N), was initiated in 1978, for the performance of which the two sodium circuits CREVONA and FARINA were constructed.. The testing programme was performed in co-operation with Siemens-KWU(Interatom), SCK Mol, AEA Risley, CEGB Leatherhead, CEN de Cadarache and EdF les Renardières. It was related to the German fast reactor SNR 300 and the European Fast Reactor Project.
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Borgstedt, H.U., Frees, G. (1995). Results of Material Testing in the “Crevona” and “Farina” Loops. In: Borgstedt, H.U., Frees, G. (eds) Liquid Metal Systems. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-1977-5_14
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DOI: https://doi.org/10.1007/978-1-4615-1977-5_14
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