Results 31 to 40 of about 1,391 (172)
Simulation of Pulsed Neutron Source Experiment in Tehran Research Reactor Core (TRR) [PDF]
مجله علوم و فنون هستهای, 2022 One of the useful methods for measuring fast neutron decay constant in a nuclear reactor core is the pulsed neutron source experiment as MCNP code is based on the Monte Carlo method, so able to track the time-dependent behavior of the particles in static
M. Arkani
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Calculation of Thermal Neutron Diffusion Length in a Light Water Media using MCNP Code [PDF]
مجله علوم و فنون هستهای, 2023 One of the key parameters of neutron diffusing media is the thermal neutron diffusion length. The popular calculational method is founded on utilizing MCNP code and curve fitting of a mathematical function to the neutron flux distribution in the media ...
M. Arkani
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Nuclear Engineering and Technology, 2015 Background: 241Am, 243Am, and 237Np isotopes are among the most radiotoxic components of spent nuclear fuel. Recently, researchers have planned different incineration scenarios for the highly radiotoxic elements of nuclear waste in critical reactors ...
Zohreh Gholamzadeh +2 more
doaj +1 more source
Loss of offsite power accident analysis in a VVER-1000/V446 nuclear power plant [PDF]
Nuclear Technology and Radiation Protection, 2019 The aim of this study is to present a thermo-hydraulic analysis of the loss of offsite power accident in VVER-1000/V446 nuclear power plant using the RELAP5 code.
Esfandiari Mohsen +3 more
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Radiation damage and yield strength calculations in the pressure vessel of WWER-1000 reactor and sensitivity analysis of neutron spectrum on the shield of vessel [PDF]
مجله علوم و فنون هستهای, 2021 Radiation damage calculation is very important for estimating the lifetime of nuclear power plant instruments. The purpose of the present study is to evaluate the sensitivity of the damage values to the neutron group energy, where the neutron flux rate ...
E. Moslemi-Mehni +3 more
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Measurement and calculation of neutron energy spectrum in TRR irradiation facilities: a feasibility study of using TRR for BNCT [PDF]
مجله علوم و فنون هستهای, 2015 An investigation has been made for the use of Tehran Research Reactor (TRR) as a neutron source for the boron neutron capture therapy (BNCT) by calculating and measuring the energy spectrum and spatial distribution of neutrons in all external irradiation
Yaser kasesaz +5 more
doaj
Effect of neutron irradiation on neat epoxy resin stability in shielding applications
Science and Engineering of Composite Materials, 2018 Epoxy resin is a thermoset polymer and is one of the main candidates for radiation shielding application. In this investigation, carbon, hydrogen, and nitrogen analysis showed that the presence of the light element of nitrogen in cured epoxy could lead ...
Adeli Ruhollah +3 more
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Nuclear Engineering and Technology, 2023 Due to neutron radiation, atomic displacement has a significant effect on material in nuclear reactors. A range of secondary displacement models, including the Kinchin-Pease (K–P), Lindhard, Norgett-Robinson-Torrens (NRT), and athermal recombination ...
Elaheh Moslemi-Mehni +3 more
doaj +1 more source
Metrology and Measurement Systems, 2017 A correlation measuring tool for an endogenous pulsed neutron source experiment is developed in this work. Paroxysmal pulses generated by a bursts of neutron chains are detected by a 10-kbit embedded shift register with a time resolution of 100 ns.
Arkani Mohammad +3 more
doaj +1 more source
Energy Science &Engineering, EarlyView.ABSTRACT Thermochemical gasification is one of the most efficient methods for producing solid waste synthesis gas. Therefore, to predict and analyze the process of gasification of municipal solid waste (MSW) in a downdraft fixed‐bed gasification reactor with a thermal capacity of 2.1 kW, a comprehensive numerical modeling approach based on Gibbs free ...
Mohammad Reza Gharib +2 more
wiley +1 more source