Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Author:

Vu Thanh Mai123,Bui Thi Hong4,Tran Le Quang Linh4

Affiliation:

1. Department of Mechanical and Nuclear Engineering, University of Sharjah , Sharjah, P.O. Box 27272, United Arab Emirates ; , Sharjah, P.O. Box 27272, United Arab Emirates ; , Hanoi, 334 Nguyen Trai, Thanh Xuan, Hanoi 120-034, Vietnam

2. Research Institute of Sciences and Engineering, University of Sharjah , Sharjah, P.O. Box 27272, United Arab Emirates ; , Sharjah, P.O. Box 27272, United Arab Emirates ; , Hanoi, 334 Nguyen Trai, Thanh Xuan, Hanoi 120-034, Vietnam

3. VNU University of Science, Vietnam National University , Sharjah, P.O. Box 27272, United Arab Emirates ; , Sharjah, P.O. Box 27272, United Arab Emirates ; , Hanoi, 334 Nguyen Trai, Thanh Xuan, Hanoi 120-034, Vietnam

4. VNU University of Science, Vietnam National University , Hanoi, 334 Nguyen Trai, Thanh Xuan, Hanoi 120-034, Vietnam

Abstract

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 The burnable poison is fixed inside the reactor while absorber rods/absorber layers are withdrawn or inserted in sequence to achieve the required excess reactivity of about 700 pcm.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

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference11 articles.

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