Results 151 to 160 of about 1,440 (170)
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Modification of the neutron beam spectrum for neutron radiography at Tehran Research Reactor (TRR)
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1996Abstract Recently due to the replacement of the High Enriched Uranium (HEU) fuel with the Low Enriched Uranium (LEU) fuel and the changes in the reactor core configuration at TRR, the existing Neutron Radiography (NR) system was no longer efficient.
K. Kamali Moghadam, F. Ziaie
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Optimization of 60Co production using neutron flux trap in the Tehran research reactor
Annals of Nuclear Energy, 2005Abstract Radioisotope production is one of the most important applications of research reactors. 60 Co has a wide application in industry and medicine. In this paper the efficient production of 60 Co by enhancing radiation systems is studied and developed by using neutron flux trap concept in Tehran research reactor.
H. Khalafi, M. Gharib
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Production of 223Ra from 226Ra in Tehran Research Reactor for treatment of bone metastases
Journal of Radioanalytical and Nuclear Chemistry, 2015In this research production of 223Ra via neutron irradiation of 226Ra nuclei was studied in Tehran Research Reactor and compared with available literature data. Dowex 1X8 and Dowex 50WX8 anion and cation exchange resins were used for isolation of produced radioisotopes.
Reza Bagheri +4 more
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Feasibility and improvement in production of 191Os/191mIr generator by Tehran Research Reactor (TRR)
Annals of Nuclear Energy, 2012Abstract This manuscript describes an investigation on the production of 191 Os/ 191m Ir by Tehran Research Reactor (TRR). 191 Os-hexachloro-osmate was obtained by thermal neutron (4 × 10 13 cm −2 s −1 ) irradiation of enriched 190 Os sample followed by fusion with KOH and KNO 3 in acidic media. One of the important radionuclide impurities is
Nafise Salek +4 more
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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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Neutronic feasibility study for neutron flux upgrading of Tehran research reactor
2023Aminfarkhani, S. Taher +2 more
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