Results 91 to 100 of about 2,139 (206)
, 2015 Increased use of radiation in medicine, industry, and laboratories, requires safe conditions to be provided for its optimal use. One of the cases in which people are exposed to radiation, is during the detection of explosive materials by PGNAA method ...
Nasrabadi, M. +3 more
core +1 more source
Monte Carlo investigation of prostate cancer ion therapy by using SOBP technique in the GEANT4 toolkit and MCNPX code [PDF]
, 2015 Regarding the useful results concerned with an external radio-therapy in treatment of tumors, we consider in this paper a standard model of the human prostate phantom based on MIRD phantom for the Monte Carlo simulation in GEANT4 toolkit and ...
Ali, Mahdipour Seyed +2 more
core +1 more source
, 2021 Introduction: Radiopharmaceuticals are widely used in modern treatment of cancer. The injection of radiopharmaceuticals into the patient’s body and its accumulation in target tissue should have most therapeutic effect on target tissue.
Shirmardi, Seyed Pezhman +2 more
core +1 more source
DOSE ESTIMATION OF THE BNCT WATER PHANTOM BASED ON MCNPX COMPUTER CODE SIMULATION
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA, 2020 Cancer is a malignant tumor that destroys healthy cells. Cancer treatment can be done by several methods, one of which is BNCT. BNCT uses 10B target which is injected into the human body, then it is irradiated with thermal or epithermal neutrons. Nuclear reaction will occur between boron and neutrons, producing alpha particle and lithium-7. The dose is
Amanda Dhyan Purna Ramadhani +6 more
openaire +2 more sources
Modeling of the CTEx subcritical unit using MCNPX code [PDF]
, 2011 The present work aims at simulating the subcritical unit of Army Technology Center (CTEx) namely ARGUS pile (subcritical uranium-graphite arrangement) by using the computational code MCNPX.
Santos, Ademir +3 more
core
Results in Physics, 2017 The present investigation has been performed on different bricks for the purpose of gamma-ray shielding. The values of the mass attenuation coefficient (µ/ρ), energy absorption buildup factor (EABF) and exposure buildup factor (EBF) were determined and ...
M.I. Sayyed +5 more
doaj +1 more source
Application of the MCNPX-McStas interface for shielding calculations and guide design at ESS [PDF]
, 2013 Recently, an interface between the Monte Carlo code MCNPX and the neutron ray-tracing code MCNPX was developed[1]. Based on the expected neutronic performance and guide geometries relevant for the ESS, the combined MCNPX-McStas code is used to calculate ...
Lauritzen, Bent +6 more
core
Results in Physics, 2019 This study focuses on radiation shielding characteristics of Li2O, Al2O3 and ZnO-doped boron phosphate glasses containing PbO and Bi2O3. Mass attenuation coefficient (μ/ρ) values of the glasses have been calculated using MCNPX code at various photon ...
H.O. Tekin +5 more
doaj +1 more source
Calculation of Photoneutron Contamination of Varian Linac in ICRU Soft-Tissue Phantom Using MCNPX Code. [PDF]
J Med Phys, 2021 Cheraghian M +3 more
europepmc +1 more source
Comparative analysis of MCNPX and GEANT4 codes for fast-neutron radiation treatment planning
Nuclear Energy and Technology, 2015 AbstractThe paper presents a comparative analysis of the MCNPX and GEANT4 simulation tools for the beam therapy fast neutron transport calculation problems. Groups of model experiments are described which compare the absorbed energy calculated values obtained on different types of phantoms and the rate of calculation for both simulation tools is ...
A.N. Solovyev +3 more
openaire +2 more sources