Zobrazeno 1 - 2
of 2
pro vyhledávání: '"M. W. Wendel"'
Publikováno v:
Nuclear Science and Engineering. 125:75-83
Analytical and numerical investigations of critical heat flux (CHF) and reactor thermal limits are conducted for oscillatory two-phase flows often associated with natural circulation conditions. The CHF and associated thermal limits depend on the amp
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2003:367