| contributor author | S. M. Ghiaasiaan | |
| contributor author | I. Catton | |
| contributor author | R. B. Duffey | |
| date accessioned | 2017-05-08T23:18:12Z | |
| date available | 2017-05-08T23:18:12Z | |
| date copyright | December, 1984 | |
| date issued | 1984 | |
| identifier issn | 0098-2202 | |
| identifier other | JFEGA4-27008#477_1.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/98607 | |
| description abstract | A quasi-steady, two-dimensional thermal hydraulic analysis of the two-phase region formed ahead of a quench front during reflooding of a slab or cylindrical core is carried out, and the results for slab geometry are compared with the experiment. It is shown that the two-phase level variation in the core is due to the transverse heat flux power profile, and is sensitive to the assumed pressure-drop boundary condition for the bundle, while the effects of crossflow and axial friction are small. Implicit expressions are given for predicting the quasi-steady two-phase level variation across slab and cylindrical cores. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Thermal Hydraulic and Two-Phase Phenomena in Reflooding of Nuclear Reactor Cores | |
| type | Journal Paper | |
| journal volume | 106 | |
| journal issue | 4 | |
| journal title | Journal of Fluids Engineering | |
| identifier doi | 10.1115/1.3243153 | |
| journal fristpage | 477 | |
| journal lastpage | 485 | |
| identifier eissn | 1528-901X | |
| keywords | Friction | |
| keywords | Slabs | |
| keywords | Boundary-value problems | |
| keywords | Nuclear reactors | |
| keywords | Geometry | |
| keywords | Pressure drop AND Heat flux | |
| tree | Journal of Fluids Engineering:;1984:;volume( 106 ):;issue: 004 | |
| contenttype | Fulltext | |
