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This report deals with the assessment of the amount of radioactive wastes arisng from hypothetical decommissioning of the power fast breeder reactor SUPER PHENIX 1. The following assumptions have been used : - activities are produced through neutronic captures in materials - the reactor has been run at full power for 30 years - results obtained assume a 2 years decay time after ultimate reactor shut down. The more active structures and components are situated along the core axis (core cover plug, diagrid, diagrid support ...). Radially beyond the core are the lateral neutron shielding assemblies which reduce primary pump and intermediate heat exchanger activation. Main contributions arise from the following isotopes: 59Co, 54Fe, 62Ni. Stellite (about 50% of 59Co) coating of spherical seats on the props in which the subassemblies are stuck, and stellite coatings on diagrid-diagrid support seats, have a high maximum local volumic activity (about 1.0 E12 and 1.0 E9 Bq/cm3) while 85% of the analysed 3000 steel tons have an activity lower than 100Bq/g. Above the roof slab and outside the safety tank, structures and components are not active.

Additional information

Authors: ALARY C, Novatome, Lyon (FR);MAIRE D, Novatome, Lyon (FR);PEYRARD G, Novatome, Lyon (FR)
Bibliographic Reference: EUR 12539 FR (1990) 129 pp., FS, ECU 11.25
Availability: (2)
Record Number: 199010278 / Last updated on: 1994-12-01
Original language: fr
Available languages: fr
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