| contributor author | D. Mukhopadhyay | |
| contributor author | P. Majumdar | |
| contributor author | G. Behera | |
| contributor author | S. K. Gupta | |
| contributor author | V. Venkat Raj | |
| date accessioned | 2017-05-09T00:08:30Z | |
| date available | 2017-05-09T00:08:30Z | |
| date copyright | May, 2002 | |
| date issued | 2002 | |
| identifier issn | 0094-9930 | |
| identifier other | JPVTAS-28417#161_1.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/127355 | |
| description abstract | The reactor channel of the horizontal core of pressurized heavy water reactors experiences very low sustained flow during loss of coolant accident (LOCA) at the reactor inlet feeders caused by certain breaks known as critical channel breaks. In this type of accident the reactor trip is delayed causing a gross mismatch of the heat generation and heat removal in the channel, thus leading to rapid temperature rise in the affected channel. A study has been carried out to identify the phenomena and the break size leading to such a situation. Severe fuel damage is predicted in the channel. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR | |
| type | Journal Paper | |
| journal volume | 124 | |
| journal issue | 2 | |
| journal title | Journal of Pressure Vessel Technology | |
| identifier doi | 10.1115/1.1463036 | |
| journal fristpage | 161 | |
| journal lastpage | 167 | |
| identifier eissn | 1528-8978 | |
| keywords | Flow (Dynamics) | |
| keywords | Heat | |
| keywords | Temperature | |
| keywords | Channels (Hydraulic engineering) | |
| keywords | Fuels | |
| keywords | Heavy water reactors | |
| keywords | Coolants | |
| keywords | Thermal analysis AND Pressure | |
| tree | Journal of Pressure Vessel Technology:;2002:;volume( 124 ):;issue: 002 | |
| contenttype | Fulltext | |
