Tensile properties of an austenitic fuel rod cladding steel after corrosion with uraniumdioxid and simulated fission products and irradiation sith neutrons.
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| Main Author: | |
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| Corporate Author: | |
| Format: | Book |
| Language: | German |
| Published: |
Karlsruhe :
Kernforschungszentrum Karlsruhe,
1993.
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| 245 | 1 | 0 | |a Tensile properties of an austenitic fuel rod cladding steel after corrosion with uraniumdioxid and simulated fission products and irradiation sith neutrons. |
| 260 | |a Karlsruhe : |b Kernforschungszentrum Karlsruhe, |c 1993. | ||
| 300 | |a 51 p. | ||
| 591 | |a inventario duplicado con ej. de E/1 OIEA S.S. 50-SG-S11A ej.3 que se pasó a HISDOC | ||
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