| contributor author | Ghosh, Sandip | |
| contributor author | Saha, Samir Kumar | |
| date accessioned | 2022-02-05T21:54:26Z | |
| date available | 2022-02-05T21:54:26Z | |
| date copyright | 3/16/2021 12:00:00 AM | |
| date issued | 2021 | |
| identifier issn | 2332-8983 | |
| identifier other | ners_007_03_034503.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4276551 | |
| description abstract | This work demonstrates the leak flow behavior of subcooled water at high pressure and high temperature through a narrow slit analogous to a pipe crack. The modeling and simulations are based on the loss of coolant accident in the primary loop piping of pressurized heavy water reactors where a subcooled liquid is subjected to a rapid depressurization. Prediction of critical leak flow pattern is crucial in the design methodology of costly high energy pipelines in the perspective of leak before break consideration. For a variety of entry and exit conditions, the interphase mass transfer has been studied using computational techniques. Presence of thermodynamic nonequilibrium was detected on several occasions due to high transit velocities. A comparison with experimental findings indicates the validity of a flashing model for safety analysis of similar high energy thermal systems. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage | |
| type | Journal Paper | |
| journal volume | 7 | |
| journal issue | 3 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4048477 | |
| journal fristpage | 034503-1 | |
| journal lastpage | 034503-8 | |
| page | 8 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 003 | |
| contenttype | Fulltext | |