Results 131 to 140 of about 1,391 (172)
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Neutronic Analysis for Tehran Research Reactor Upgrading
10th International Conference on Nuclear Engineering, Volume 4, 2002This paper presents preliminary results of a study undertaken to investigate the possibility of raising the power of Tehran Research Reactor (TRR) from 5 to 10 MW (th), keeping the same core configuration and with minimum changes in the primary cooling circuit. The main aim of TRR upgrade is to increase the volume of radioisotope production.
Ebrahim Afshar, Alireza Shahidi
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Feasibility study for Tehran Research Reactor power upgrading
Annals of Nuclear Energy, 2008Abstract The present work is concerned with a power upgrading study of Tehran Research Reactor (TRR). The upgrading study is aimed at investigating the possibility of raising power of the TRR from the current level of 5 MW th to a higher level without violating the original thermal-hydraulic safety criteria. The existing core, comprising 22 standard
Kazem Farhadi, Samad Khakshournia
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Study on secondary shutdown systems in Tehran research reactor
Nuclear Engineering and Design, 2015Abstract One important safety aspect of any research reactor is the ability to shut down the reactor. Usually, research reactors, currently in operation, have a single shutdown system based on the simultaneous insertion of the all control rods into the reactor core through gravity.
H.R. Jalali, A.H. Fadaei, M. Gharib
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Calculational tools to conduct experimental optimization in Tehran research reactor
Annals of Nuclear Energy, 1999Abstract Utilization of irradiation facilities in Tehran research reactor (TRR) requires proper computational tools to deliver accurate and precise results. In this paper validity of different schemes are checked against experimental measurements.
H Khalafi, M Gharib
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Sensitivity Analysis of Kinetics Parameters of Tehran Research Reactor (TRR)
Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 2009In this research, effective delayed neutron fraction (βeff) and neutron generation time (Λ) of the Tehran Research Reactor (TRR) are calculated for different uranium enrichments from 14.84 w/o to 96.56 w/o U235 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 ...
Seyed Abolfazl Hosseini, Naser Vosoughi
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Annals of Nuclear Energy, 2009
Abstract Cherenkov radiation is a process that could be used as an extra channel for power measurement to enhance redundancy and diversity of a reactor. This is especially easy to establish in a pool type research reactor. A simple photo diode array is used in Tehran Research Reactor to measure and display power in parallel with the existing ...
M. Arkani, M. Gharib
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Abstract Cherenkov radiation is a process that could be used as an extra channel for power measurement to enhance redundancy and diversity of a reactor. This is especially easy to establish in a pool type research reactor. A simple photo diode array is used in Tehran Research Reactor to measure and display power in parallel with the existing ...
M. Arkani, M. Gharib
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Proposition of innovative and safe design of grid plate for Tehran research reactor
Annals of Nuclear Energy, 2017Abstract The purpose of this paper is to propose an innovative and safe design of grid plate for Tehran research reactor (TRR) without any reduction in its performance in comparison with the current operation. The new grid plate consisted of two joined cubic with empty walls which are place of fuels and heavy water, respectively.
H.R. Jalali, A.H. Fadaei
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Thermo-Hydraulic Calculation and Safety Analysis of the Tehran Research Reactor
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009The aim of this study is to evaluate the thermal hydraulic parameters such as, Minimum DNBR, fuel, clad and coolant temperatures of the Tehran Research Reactor (TRR) core in order to assure that the thermal limitations are not exceeded at full power and steady-state and the loss-of-flow accident (LOFA) operating conditions and the existing design is ...
JAFARI J +4 more
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Safety requirement assessment of fuel sample test in Tehran research reactor
Progress in Nuclear Energy, 2016Abstract In the present study, neutronic and thermo-hydraulic evaluation and the feasibility study of inserting a fissile material into the Tehran research reactor core are performed. The feasibility study is carried out by calculating safety related neutronic parameters of the core, i.e., excess reactivity, shutdown margin, reactivity worth of the ...
Farrokh Khoshahval, Amin Davari
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A model for the analysis of pump start-up transients in Tehran Research Reactor
Progress in Nuclear Energy, 2007During the starting up period of a centrifugal pump the rotational speed is accelerated rapidly from standstill to its final speed and then established at the rated speed. While flow rate and total dynamic pressure rise are boosted accordingly. In the point of view of a theoretical treatment, pump start-up offers difficulty because both rotational ...
FARHADI K. +2 more
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