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
doaj +1 more source
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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Data-based fault detection in chemical processes: Managing records with operator intervention and uncertain labels [PDF]
, 2016 Developing data-driven fault detection systems for chemical plants requires managing uncertain data labels and dynamic attributes due to operator-process interactions.
Askarian, Mahdieh +3 more
core +1 more source
EU-Iran Relations in the Post-JCPOA Period: Selected Political Aspects [PDF]
, 2018 After the 1979 revolution, Europe’s policy of engaging Iran differed from the American approach. The circumstances changed in 2002, when the international community learnt about the undeclared nuclear sites at Arak and Natanz, as well as the scale of the
Osiewicz, Przemysław
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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
doaj +1 more source
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
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
Thermal-hydraulic analysis of loss-of-cooling accident in spent fuel pool of Bushehr NPP using the RELAP5 and MELCOR [PDF]
مجله علوم و فنون هستهای, 2020 Following the Fukushima Daiichi accident, the simulation of accidents related to the Spent Fuel Pool (SFP) became more important due to the high content of long-lived radionuclides, and lack of the protection by the pressure vessel despite its low decay ...
S. Gol Narges, S.Kh. Mousavian
doaj +1 more source