Status and perspective of two-phase flow modelling in the neptune multiscale thermal-hydraulic platform for nuclear reactor simulation /
Spremljeno u:
| Glavni autor: | Bestion, Dominique. |
|---|---|
| Daljnji autori: | Den, Cea-Grenoble., Guelfi, Antoine. |
| Format: | Članak |
| Jezik: | English |
| Teme: | |
| Oznake: |
Dodaj oznaku
Bez oznaka, Budi prvi tko označuje ovaj zapis!
|
| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
|---|
Similar Items
- Development and preliminary assessment of a three-dimensional thermal hydraulics code, CUPID /
-
Extension of CFD codes application to two-phase flow safety problems /
od: Bestion, D. -
A simple analytical method for nonlinear density wave two-phase instability in a sodium-heated and helically coiled steam generator /
od: Kim, Seong-O. - Experiments on the performance sensitivity of the passive residual heat removal system of an advanced integral type reactor /
-
Development of interfacial area transport equation /
od: Ishii, Mamoru.