| contributor author | Marأ،czy, Csaba | |
| contributor author | Hegyi, Gyأ¶rgy | |
| contributor author | Trosztel, Istvأ،n | |
| contributor author | Temesvأ،ri, Emese | |
| date accessioned | 2017-05-09T01:32:08Z | |
| date available | 2017-05-09T01:32:08Z | |
| date issued | 2016 | |
| identifier issn | 2332-8983 | |
| identifier other | NERS_2_1_011004.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/162172 | |
| description abstract | The aim of the supercritical water reactorfuel qualification test (SCWRFQT) EuratomChina collaborative project is to design an experimental facility for qualification of fuel for the supercritical watercooled reactor. The facility is intended to be operated in the LVR15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the threedimensional (3D) coupled neutronicthermohydraulic steadystate and transient analysis of LVR15 with the fueled loop. Conservatively calculated enveloping parameters (e.g.,آ reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3DATHLETcoupled dynamic code. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Control Rod Withdrawal Analysis of the Supercritical Water Reactor Fuel Qualification Test Facility in the LVR 15 Research Reactor | |
| type | Journal Paper | |
| journal volume | 2 | |
| journal issue | 1 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4030933 | |
| journal fristpage | 11004 | |
| journal lastpage | 11004 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001 | |
| contenttype | Fulltext | |