| 摘要 |
<p>Austenitic steel intended for use in radiation areas of nuclear reactors is largely resistant to irradiation-induced stress corrosion cracking if its silicon, phosphorus and sulfur contents are reduced in relation to standard commercial steel quantities and its grain structure has finely dispersed carbide precipitation, particularly of niobium carbide. The finely dispersed distribution can be induced in that larger niobium precipitation takes place at annealing temperatures between 1100 and 1150 °C, and carbide is precipitated through the corresponding annealing at temperatures of approximately 750 °C.</p> |
