Düz Mehtap, İnal Selcan
Physics Department, Science and Art Faculty, İnönü University, Malatya, Turkey.
Institute of Science, İnönü University, Malatya, Turkey.
Sci Rep. 2020 Dec 17;10(1):22114. doi: 10.1038/s41598-020-79236-8.
In this study, a Boiling Water Reactor (BWR) modeling was done for the reactor core divided into square lattice 8 × 8 type using the Monte Carlo Method. Each of the square lattices in the reactor core was divided into small square lattices 7 × 7 type in groups of four. In the BWR designed in this study, modeling was made on fuel assemblies at pin-by-pin level by using neptunium mixed fuels as fuel rod, Zr-2 and SiC as fuel cladding, HO as coolant. In fuel rods were used NpO and NpF fuels at the rate of 0.2%-1% as neptunium mixed fuels. In this study, the effect on the neutronic calculations as k, neutron flux, fission energy, heating of NpO and NpF fuels in 0.2%-1% rates, and Zr-2 and SiC clads were investigated in the designed BWR system. The three-dimensional (3-D) modelling of the reactor core and fuel assembly into the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.
在本研究中，使用蒙特卡罗方法对分为8×8型方形晶格的反应堆堆芯进行了沸水反应堆（BWR）建模。反应堆堆芯中的每个方形晶格又被分成四个一组的7×7型小方形晶格。在本研究设计的沸水反应堆中，以逐针水平对燃料组件进行建模，使用钚混合燃料作为燃料棒，Zr-2和SiC作为燃料包壳，水作为冷却剂。在燃料棒中，使用0.2%-1%比例的NpO和NpF燃料作为钚混合燃料。在本研究中，研究了在设计的沸水反应堆系统中，0.2%-1%比例的NpO和NpF燃料以及Zr-2和SiC包壳对中子学计算（如反应性k、中子通量、裂变能、发热）的影响。使用MCNPX-2.7.0蒙特卡罗方法和ENDF/B-VII.0核数据库对设计的沸水反应堆系统中的反应堆堆芯和燃料组件进行了三维（3-D）建模。
