Loading...
Search for:
effective-delayed-neutron-fraction
0.012 seconds
Calculation and measurement of kinetics parameters of Tehran research reactor
, Article International Conference on Nuclear Engineering, Proceedings, ICONE, 12 July 2009 through 16 July 2009, Brussels ; Volume 5 , 2009 , Pages 223-228 ; 9780791843550 (ISBN) ; Vosoughi, N ; Gharib, M ; Ghofrani, M. B ; Sharif University of Technology
Abstract
Effective delayed neutron fraction βeff and neutron generation time Λare important factors in reactor physics calculation and transient analysis. In first stage of this research, these kinetics parameters have been calculated for two states of Tehran research reactor (TRR), i.e. cold (fuel, clad and coolant temperature 20°C) and hot (fuel, clad and coolant temperature 65, 49 and 44°C, respectively) using MTR-PC code. In second stage, these parameters have been measured with experimental method based on Inhour equation. For cold state, calculated βeff and Λ by MTR-PC are 0.008315 and 30.190 μsec, respectively. Same parameters in hot state are 0.008303 and 33.828 μsec, respectively. The...
Kinetic parameters evaluation of PWRs using static cell and core calculation codes
, Article Annals of Nuclear Energy ; Volume 41 , 2012 , Pages 110-114 ; 03064549 (ISSN) ; Malmir, H ; Sharif University of Technology
Abstract
In this paper, evaluation of the kinetic parameters (effective delayed neutron fraction and prompt neutron lifetime) in PWRs, using static cell and core calculation codes, is reported. A new software has been developed to link the WIMS, BORGES and CITATION codes in Visual C# computer programming language. Using the WIMS cell calculation code, multigroup microscopic cross-sections and number densities of different materials can be generated in a binary file. By the use of BORGES code, these binary-form cross-sections and number densities are converted to a format readable by the CITATION core calculation code, by which the kinetic parameters can be finally obtained. This software is used for...
Monte Carlo simulation of Feynman-α and Rossi-α techniques for calculation of kinetic parameters of Tehran research reactor
, Article Annals of Nuclear Energy ; Volume 38, Issue 10 , 2011 , Pages 2140-2145 ; 03064549 (ISSN) ; Vosoughi, N ; Hosseini, M ; Sharif University of Technology
Abstract
Noise analysis techniques including Feynman-α (variance-to-mean) and Rossi-α (correlation) have been simulated by MCNP computer code to calculate the prompt neutron decay constant (α0), effective delayed neutron fraction (βeff) and neutron generation time (Λ) in a subcritical condition for the first operating core configuration of Tehran Research Reactor (TRR). The reactor core is considered to be in zero power (reactor power is less than 1 W) in the entire simulation process. The effect of some key parameters such as detector efficiency, detector position and its dead time on the results of simulation has been discussed as well. The results of proposed method in the current study are...
Uncertainty evaluation of calculated and measured kinetics parameters of Tehran Research Reactor
, Article Nuclear Engineering and Design ; Volume 240, Issue 10 , 2010 , Pages 2761-2767 ; 00295493 (ISSN) ; Vosoughi, N ; Sharif University of Technology
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 kinetics parameters have been calculated for two states of Tehran Research Reactor (TRR), i.e. cold (fuel, clad and coolant temperature 20 °C) and hot (fuel, clad and coolant temperature 65, 49 and 44 °C, respectively) states using MTR-PC computer code. The ratio of (βeff) i/(βeff)core plays an important role in reactivity accident analysis codes. This parameter and its contribution to effective delayed neutron fraction from each nucleus have been calculated in cold and hot reactor states. Uncertainty 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...