Recommendations for calculating the characteristics of thermal creep of mixed uranium–plutonium oxide fuel when analyzing fuel-element serviceability

✍ Scribed by V. B. Malygin; K. V. Naboichenko; A. S. Shapovalov; Yu. K. Bibilashvili

• Publisher: Springer US
• Year: 2010
• Tongue: English
• Weight: 134 KB
• Volume: 108
• Category: Article
• ISSN: 1573-8205
• DOI: 10.1007/s10512-010-9250-y