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Sensitivity analysis of the transmission factor and resolution of a multiblade neutron velocity selector to the various parameters
, Article Radiation Physics and Chemistry ; Volume 177 , December , 2020 ; Hosseini, S. A ; Sharif University of Technology
Elsevier Ltd
2020
Abstract
The neutron velocity selector is a device used to produce a monochromatic neutron beam with continuous flux. The purpose of the present study is to investigate the sensitivity of the transmission factor and resolution of a multiblade neutron velocity selector to the various parameters using the McStas software. To this end, two instruments were created using the Arm, Progress_bar, Source_simple, DivMonitor, L_monitor, Guide_channeled and V_selector components of the McStas software. The used V_selector component to simulate the multiblade neutron velocity selector was created by considering three assumptions: 1. The absorption of colliding neutrons to selector blades, 2. No interaction of...
Calculation, measurement and sensitivity analysis of kinetic parameters of tehran research reactor
, Article Annals of Nuclear Energy ; Volume 37, Issue 4 , April , 2010 , Pages 463-470 ; 03064549 (ISSN) ; Vosoughi, N ; Ghofrani, M. B ; Gharib, M ; Sharif University of Technology
2010
Abstract
Effective delayed neutron fraction βeff and neutron generation time Λ are important factors in reactor physics calculation and transient analysis. In the first stage of this research, these kinetic parameters have been calculated for two states of Tehran Research Reactor (TRR), i.e. cold (fuel, clad and coolant temperatures equal to 20 °C) and hot (fuel, clad and coolant temperatures of 65, 49 and 44 °C, respectively) states using MTR_PC code. In the second stage, these parameters have been measured with an experimental method based on Inhour equation. For the cold state, calculated βeff and Λ by MTR_PC code are 0.008315 and 30.190 μs, respectively. In the hot state, these parameters being...
Sensitivity analysis of kinetics parameters of Tehran Research Reactor (TRR)
, Article 17th International Conference on Nuclear Engineering, 12 July 2009 through 16 July 2009 ; Volume 5 , 2009 , Pages 419-423 ; 9780791843550 (ISBN) ; Vosoughi, N ; Nuclear Engineering Division, ASME; The Japan Society of Mechanical Engineers, JSME; The Chinese Nuclear Society, CNS ; Sharif University of Technology
Abstract
In this research, effective delayed neutron fraction (βeff) and neutron generation time (A) of the Tehran Research Reactor (TRR) are calculated for different uranium enrichments from 14.84 w/o to 96.56 w/o U 235 in two states of the TRR, (cold fuel, clad and coolant temperature of 20°C; and hot fuel, clad and coolant temperature of 65, 49 and 44°C, respectively) using the MTR-PC computer code. Comparative analysis shows that both βeff and Λ increase as fuel enrichment decreases. However, variation rate βeff is not the same in two conditions. βeff in the hot state is larger than those calculated in the cold state when fuel enrichment goes more than 83.91%, while the situation is reverse for...