Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 2005.05a
- /
- Pages.23-24
- /
- 2005
Evaluation of a CFD Code CFX-5 for Predicting the Inlet Nozzle Flows of the CANDU-6 Moderator System
-
Yoon, Churl
(Korea Atomic Energy Research Institute)
;
-
Min, Byung-Joo
(Korea Atomic Energy Research Institute)
- Published : 2005.05.26
Abstract
Keywords