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Tensile properties of an austenitic fuel rod cladding steel after corrosion with uraniumdioxid and simulated fission products and irradiation sith neutrons.

By: Contributor(s): Material type: TextTextLanguage: de Publication details: Karlsruhe : Kernforschungszentrum Karlsruhe, 1993.Description: 51 pISSN:
  • 0303-4003
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