Analyses of fluid flow and heat transfer inside calandria vessel of candu-6 reactor using CFD /
Wedi'i Gadw mewn:
| Prif Awdur: | Yu, Seon-Oh. |
|---|---|
| Awduron Eraill: | Kim, Hho-Jung., Kim, Manwoong. |
| Fformat: | Erthygl |
| Iaith: | English |
| Pynciau: | |
| Tagiau: |
Ychwanegu Tag
Dim Tagiau, Byddwch y cyntaf i dagio'r cofnod hwn!
|
| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
|---|
Eitemau Tebyg
-
CFD application to the regulatory assessment of fac-caused CANDU feeder pipe wall thinning issue /
gan: Kang, Dong-Gu. -
Development of best practice guidelines for CFD in nuclear reactor safety /
gan: Mahaffy, J. -
A review of CANDU feeder wall thinning /
gan: Chung, H.-S. -
Assessment of CFD codes used in nuclear reactor safety simulations /
gan: Smith, B.L.. -
Extension of CFD codes application to two-phase flow safety problems /
gan: Bestion, D.