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Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR
, Article Nuclear Engineering and Technology ; Volume 52, Issue 12 , 2020 , Pages 2852-2859 ; Ayyoubzadeh, S. M ; Terman, M. S ; Sharif University of Technology
Korean Nuclear Society
2020
Abstract
This paper deals with the simulation-based design optimization and experimental validation of the characteristics of an in-core silver Self-Powered Neutron Detector (SPND). Optimized dimensions of the SPND are determined by combining Monte Carlo simulations and analytical methods. As a first step, the Monte Carlo transport code MCNPX is used to follow the trajectory and fate of the neutrons emitted from an external source. This simulation is able to seamlessly integrate various phenomena, including neutron slowing-down and shielding effects. Then, the expected number of beta particles and their energy spectrum following a neutron capture reaction in the silver emitter are fetched from the...
An investigation on the improvement of neutron radiography system of the tehran research reactor by using MCNPX simulations
, Article Nuclear Engineering and Technology ; Volume 53, Issue 10 , 2021 , Pages 3413-3420 ; 17385733 (ISSN) ; Zamzamian, M ; Fadaei, A. H ; Gharib, M ; Feghhi, A. H ; Sharif University of Technology
Korean Nuclear Society
2021
Abstract
Applying the available neutron flux for medical and industrial purposes is the most important application of research reactors. The neutron radiography system is used for non-destructive testing (NDT) of materials so that it is one of the main applications of nuclear research reactors. One of these research reactors is the 5 MW pool-type light water research reactor of Tehran (TRR). This work aims to investigate on materials and location of the beam tube (BT) of the TRR radiography system to improve the index parameters of BT. Our results showed that a through-type BT with 20 cm thick carbon neutron filter, 1.2 cm and 9.4 cm of the diameter of inlet (D1) and output (D2) BT, respectively...
Effective point kinetic parameters calculation in Tehran research reactor using deterministic and probabilistic methods
, Article Nuclear Science and Techniques ; Volume 28, Issue 12 , 2017 ; 10018042 (ISSN) ; Abbaspour, A ; Sharif University of Technology
Abstract
The exact calculation of point kinetic parameters is very important in nuclear reactor safety assessment, and most sophisticated safety codes such as RELAP5, PARCS, DYN3D, and PARET are using these parameters in their dynamic models. These parameters include effective delayed neutron fractions as well as mean generation time. These parameters are adjoint-weighted, and adjoint flux is employed as a weighting function in their evaluation. Adjoint flux calculation is an easy task for most of deterministic codes, but its evaluation is cumbersome for Monte Carlo codes. However, in recent years, some sophisticated techniques have been proposed for Monte Carlo-based point kinetic parameters...
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...
Study on Immobilization of the Spent Ion Exchange Resins of Tehran Research Reactor in Borosilicate Glass
, M.Sc. Thesis Sharif University of Technology ; Samadfam, Mohammad (Supervisor) ; Yadollahi, Ali (Supervisor) ; Sepehrian, Hamid (Co-Supervisor)
Abstract
Considering the operation of the current nuclear reactors and the country's policy to achieve 10,000 megawatts of nuclear power in the horizon of 1420, as well as the construction of research reactors, we will face a huge amount of radioactive waste in the coming years. Meanwhile, spent ion exchange resins constitute a large amount of low and intermediate level (LILW) solid radioactive waste produced from the nuclear industry. Therefore, appropriate precautionary measures should be taken for the immobilization and disposal of these radioactive wastes in order to ensure the sustainable development of the nuclear industry and the protection of the environment and human health. In this study,...
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...
Design, construction and simulation of a multipurpose system for precision movement of control rods in nuclear reactors
, Article Annals of Nuclear Energy ; Volume 37, Issue 12 , 2010 , Pages 1659-1665 ; 03064549 (ISSN) ; Aghanajafi, C ; Sadoughi, S ; Sharifloo, N ; Sharif University of Technology
Abstract
This article presents the design and implementation of a microcontroller-based system for the automatic movement of control rods in nuclear reactors of either power or research types. This system is controlled automatically, is linked to a personal computer system, and has manual controlling ability as well. The important features of this system are: automatic scram of the control rods, activation of alarm in emergency situations, and the ability to tune the control rod movement course both upwards and downwards. In this system, a small tank has been improvised as a coolant reservoir for pool type reactors such as Tehran Research Reactor and its water level is continuously adjusted by...
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...