Abstract
In this paper, we report the status of development of two computer codes for bench mark rod bundle thermal hydraulic analysis using the boundary-fitted coordinate method. A classification of the flow in rod bundles is made and details of two computer codes are given. The two codes solve essentially identical sets of conservation of mass, momentum and energy, but one of them treats the fully-elliptic set of equations, and the other neglects the axial diffusion of momentum and heat. The neglect of streamwise diffusion mades the flow partially-elliptic, and brings significant reductions in computer storage, and modest savings in required computer time. Results of some validation calculations are presented with applications to reactor geometries.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 123-135 |
| Number of pages | 13 |
| Journal | Nuclear Engineering and Design |
| Volume | 62 |
| Issue number | 1-3 |
| DOIs | |
| State | Published - Dec 1980 |
| Externally published | Yes |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- General Materials Science
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering