核工程
中子
临界性
物理
核物理学
中子通量
沸水堆
中子数
瞬发中子
中子源
中子温度
缓发中子
环境科学
中子截面
工程类
作者
Indrajeet Singh,Indrajeet Singh,Pradeep Baraila,Kanchhi Singh,Umashankari Kannan
标识
DOI:10.1016/j.nuclphysbps.2023.08.005
摘要
During the refuelling and criticality of Boiling Water Reactors (BWR), fission counters are used as Source Range neutron Monitors (SRMs) to get the count rates. The study shows that the neutron counts due to spontaneous fission sources are insufficient to meet the SRM's limitations of 3 counts per second (cps). In this work, TAPS fuel assembly is modelled using the lattice transport code DRAGON5, and lattice parameters are generated as a function of fuel depletion. These parameters have been further used to model the reload-2 of the BWR core. 3D diffusion theory code KINFIN is used to simulate the BWR core with external neutron sources to estimate the neutron flux at three SRM locations. Thermal fluxes are then used to compute the neutron count rates using the sensitivity of SRMs for different combinations of five Sb-Be neutron sources.
科研通智能强力驱动
Strongly Powered by AbleSci AI