Results 201 to 210 of about 105,114 (238)
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Integral boundary layer heat transfer modeling for Tehran Research Reactor
Progress in Nuclear Energy, 2011Abstract In the present work the validity of applying the Boussinesq approximation in the analysis of natural convection heat transfer along nuclear fuel plates with large coolant channel aspect ratios is evaluated. The Boussinesq approximation is introduced into the integral boundary layer equations governing the system to describe the velocity and ...
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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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International Journal of Nuclear Energy Science and Technology, 2019
Thermal neutron flux enhancement is an essential objective to achieve more radioisotope production in the research reactors. Here, the effect of graphite reflector replacement with other customary reflectors on thermal neutron flux enhancement of Tehran ...
Z. Gholamzadeh +3 more
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Thermal neutron flux enhancement is an essential objective to achieve more radioisotope production in the research reactors. Here, the effect of graphite reflector replacement with other customary reflectors on thermal neutron flux enhancement of Tehran ...
Z. Gholamzadeh +3 more
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Journal of Radioanalytical and Nuclear Chemistry, 2016
This paper presents the early radioxenon emission inventory for Tehran research reactor (TRR) based on comparison of the two computational analyses of MCNPX2.6 and ORIGEN 2.1. To determine the possible xenon isotopic signature of TRR’s releases under normal operational condition, the TRR fresh fuel burn-up through a total 400 days operational reactor ...
Pouneh Tayyebi +4 more
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This paper presents the early radioxenon emission inventory for Tehran research reactor (TRR) based on comparison of the two computational analyses of MCNPX2.6 and ORIGEN 2.1. To determine the possible xenon isotopic signature of TRR’s releases under normal operational condition, the TRR fresh fuel burn-up through a total 400 days operational reactor ...
Pouneh Tayyebi +4 more
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Improving the NAA laboratory pneumatic transfer system for using Tehran research reactor
Annals of Nuclear Energy, 2008Abstract Neutron activation analysis (NAA) is a precise multi-elemental method which performs well for qualitative and quantitative analyses. This method has been applied to the laboratory of Radiation Applications Research School (RARS) at University of Tehran.
H. Khalafi, F. Rahmani
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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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The Boron Neutron Capture Therapy Research Facility at the Tehran Research Reactor (TRR)
1996In this paper, the procedure applied to produce a neutron beam suitable for Boron Neutron Capture Therapy (BNCT) research at the Tehran Research Reactor (TRR) is discussed. In this project the reactor core of the Nuclear Research Center of the Atomic Energy Organization of Iran was used as the neutron source.
M. K. Marashi, A. Pazirandeh
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Experimental measurements of Na-24 activity in Tehran Research Reactor (TRR)
Progress in Nuclear Energy, 2010Abstract Experimental determination of coolant activity due to Na-24 produced as a result of 23 Na(n,γ) 24 Na and 27 Al(n,α) 24 Na reactions has been done for TRR. Activity of various water samples from the reactor pool was measured. Relative Source Strength Measurement (RSSM) technique was employed to measure Na-24 activity.
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Radiation dose calculations for an accidental release from the Tehran Research Reactor
Nuclear Engineering and Design, 2013Abstract Radiological consequence analysis is carried out for a postulated accidental airborne radionuclide release from the Tehran Research Reactor (TRR). Using the “Hots pot” computer code, Total Effective Dose Equivalent (TEDE) values to the public for various atmospheric stability classes are calculated as a function of downwind distances.
Nahid Sadeghi +2 more
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Optimal placement of fixed in-core detectors for Tehran Research Reactor using information theory
Progress in nuclear energy (New series), 2018Monitoring of neutron flux distribution is very important in safe operation of both research reactors and nuclear power plants. Most challenging issue in design and implementation of online flux mapping systems is to determine optimal locations of the ...
M. S. Terman, N. M. Kojouri, H. Khalafi
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