Predictions of critical heat flux using the ASSERT-PV subchannel code for a CANFLEX variant bundle /
Đã lưu trong:
| 主要作者: | Onder, Ebru Nihan. |
|---|---|
| 其他作者: | Leung, Laurence Kim-Hung., Rao, Yanfei. |
| 格式: | Bài viết |
| 语言: | English |
| 主题: | |
| 标签: |
添加标签
没有标签, 成为第一个标记此记录!
|
| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
|---|
相似书籍
-
Nupec BFBT subchannel void distribution analysis using the matra and mars codes /
由: Hwang, Dae-Hyun. -
Comparison of dryout power data between canflex MK-V and canflex MK-IV bundle strings in uncrept and crept channels /
由: Jun, Ji Su. - An experimental study on post-chf heat transfer for low flow of water in a 3x3 rod bundle /
-
Assertiveness : practical approach /
由: Holland, Stephanie.
出版: (1990) -
Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor /
由: Jun, Ji-Su.