Low energy neutron propagation in MCNPX and GEANT4 [PDF]
Simulations of neutron background from rock for underground experiments are presented. Neutron propagation through two types of rock, lead and hydrocarbon material is discussed.
Alner +13 more
core +5 more sources
Gamma Shielding Experiment Simulation utilizing MCNPX Code
Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, radiation exposure involves people during the experiment.
Shafiqul Islam Faisal +1 more
doaj +3 more sources
Simulation of vanadium-48 production using MCNPX code [PDF]
Vanadium-48 was produced through the irradiation of the natural titanium target via the natTi(p, xn)48V reaction. The titanium target was irradiated at 1 mA current and by a 21 MeV proton beam for 4 hours. In this paper, the activity of 48V, 43Sc, and
Sadeghi Mahdi +3 more
doaj +2 more sources
Influence of dead layer on the response function of planar and coaxial Ge detector using Monte Carlo method [PDF]
Germanium crystals have a dead layer that causes a decrease in efficiency since the layer is not useful for detection but strongly attenuates photons. The thickness of this inactive layer is not well known due to the existence of a transition zone where ...
R. A. El-Tayebany, N. Shaaban
doaj +1 more source
Design of irradiation box of topaz stones and its neutronic and thermal analysis in Tehran Research Reactor [PDF]
This paper aims to design a suitable irradiation box of topaz stones and improve the neutronic parameters by maintaining the necessary conditions for their cooling in Tehran Research Reactor (TRR).
Z. Zarei +3 more
doaj +1 more source
A comprehensive GATE Monte Carlo model for a double scattering proton treatment nozzle [PDF]
Proton beam therapy (PBT) is a modern radiotherapy technique characterized by superior target coverage compared to conventional modalities. In this work, a comprehensive GATE Monte Carlo model was developed and then validated for a double scattering ...
E. Piruzan, N. Vosoughi, H. Mahani
doaj +1 more source
Transient parameters analysis of non-scrammed local melting accident scenarios using MCNPx and COBRA/EN [PDF]
The risk assessment of local nuclear fuel melting in nuclear power plants (NPPs) due to its localized nature and the difficulty in accurate monitoring is of vital importance for safe operation of nuclear reactors.
B. Salmassian, +3 more
doaj +1 more source
Dosimetry calculations of 166Dy/166Ho –Chitosan in vivo generator using GEANT4 and MCNPX [PDF]
The Holmium-166 radionuclide is one of the most effective radionuclides used to treat bone marrow cancer and rheumatoid arthritis. Among the recommended radionuclides used in radiation synovectomy, 166Ho has got much attention due to suitable decay ...
N. Salek, S. Vosoughi, A. Bahrami Samani
doaj +1 more source
Dose rate estimation of gamma-rays emitted from a LEU miniature plate [PDF]
The LEU miniature plate irradiated in the Tehran Research Reactor, which produces the radioisotope molybdenum-99, is a radioactive source consisting of various radioisotopes.
S.M. Miremad, A.B. Samani, S.S. Sayyahi
doaj +1 more source
Research Paper: Nuclear Designing of a Blood Irradiator Facility for Research and Medical Applications Using Cobalt-60 Line Sources [PDF]
Nowadays, the irradiation of blood and blood products, as well as sterilization of pharmaceuticals and biological materials used in the medical industry, are being carried out in developed countries and some developing countries. Usually for this purpose,
Reza Bagheri, Hassan Ranjbar
doaj +1 more source

