| contributor author | Vu, Thanh Mai | |
| contributor author | Bui, Thi Hong | |
| contributor author | Tran, Le Quang Linh | |
| date accessioned | 2024-04-24T22:43:07Z | |
| date available | 2024-04-24T22:43:07Z | |
| date copyright | 1/29/2024 12:00:00 AM | |
| date issued | 2024 | |
| identifier issn | 2332-8983 | |
| identifier other | ners_010_02_021503.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4295743 | |
| description abstract | 200 MWth lead-cooled fast reactor (LOTUS) reactor core is a small modular lead-cooled fast reactor with designed power of 200 MWth under development at Vietnam National University (VNU) University of Science, Hanoi for a floating nuclear power plant application. For that purpose, advanced passive safety features and no refueling requirement are the priorities in the core design process. To endure the continuous operation over a long lifetime, the startup core exhibits excess reactivity to cover the reactivity loss due to burnup. The reactivity control system includes burnable poison and absorber rods and layers made of B4C which are employed in the reactor to minimize the excess reactivity of the core to about 1 $ to enhance the safety features of the core. The burnable poison is fixed inside the reactor while absorber rods/absorber layers are withdrawn or inserted in sequence to achieve the required excess reactivity of about 700 pcm. The reactivity control was arranged into ten steps to achieve the operating time of 15 effective full-power years without refueling. Good neutronic behavior of the core was observed with negative fuel temperature coefficient and coolant void reactivity and maximum radial power peaking factor of 1.32. However, a quite large residual absorption caused by fixed burnable poison inside fuel assemblies was revealed. In further study, to increase the neutron absorption efficiency of burnable poison in the fast spectrum as well as the reactor lifetime, a neutron moderator will be considered to add to the burnable poison rods. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor | |
| type | Journal Paper | |
| journal volume | 10 | |
| journal issue | 2 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4063739 | |
| journal fristpage | 21503-1 | |
| journal lastpage | 21503-7 | |
| page | 7 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 002 | |
| contenttype | Fulltext | |