Results 161 to 170 of about 2,139 (206)

Prediction of palladium-103 production using the Monte Carlo code MCNPX

Annals of Nuclear Energy, 2013
Abstract The radionuclide 103 Pd ( T 1/2  = 16.991 d; decays almost exclusively by EC to 103m Rh, T 1/2  = 56.114 min) has been of great interest in prostate and eye cancer therapy due to its suitable half-life and decay characteristics. 103 Pd has been produced by proton irradiation of a 103 Rh target through the 103 Rh(p,n) 103 Pd reaction.
Mahmodi, M., Sadeghi, M., Tenreiro, C.
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Modeling NE213 scintillator response to neutrons using an MCNPX-PHOTRACK hybrid code

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2013
This paper reports on how to generate the response function of an NE213 scintillator when exposed to mono-energetic neutrons using the PTRAC card of the MCNPX code. The light transport part of the simulation has been undertaken with the Monte Carlo PHOTRACK code.
M Tajik, N Ghal-Eh, H Afarideh
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Modelling radiation transport in voxel geometries with the Monte Carlo code MCNPX

, 2004
The paper summarizes the research activities at ENEA Bologna to develop a voxel option within the Monte Carlo code MCNPX. An integrated methodology (MCNPX-VOXEL) has been presented that solves the radiation transport problem in voxel geometries and is based on an extension of the Monte Carlo Code MCNPX. A set of medical data (e.g.
G. Gualdrini, Daffara, Claudia, K. W. Burn, M. Pierantoni, P. Ferrari   +4 more
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Comparison of MCNPX and FLUKA Monte Carlo codes in the simulating a nuclear gauge

Applied Radiation and Isotopes, 2021
In this paper, a nuclear gauge was simulated using MCNPX and FLUKA codes. This device consists of a fluid-containing vessel, three BC400 rod plastic scintillator and a60Co gamma source. Simulation studies show that the changes in the count of each of the three detectors and the sum of their counts decrease with increasing vessel water height.
Saeid, Mohtaram, Mojtaba, Tajik, Reza Gholipour, Peyvandi   +2 more
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Photonuclear physics modeling in the MCNPX-PoliMi code

2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012
The MCNP-PoliMi code is an enhanced version of the MCNP4c code developed in 2003 to simulate the detector response from correlated neutron and gamma-ray measurements. In 2012 the -PoliMi modifications were incorporated into version 2.7.0 of the MCNPX code.
Shaun D. Clarke, Sara A. Pozzi, Enrico Padovani   +2 more
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MCNPX–BUCAL1 code to code verification through burnup analysis

Annals of Nuclear Energy, 2013
Abstract The availability of accurate burnup data is an essential first step in any systematic approach to enhancement of economics, safety and performance of a research reactor. This first step requires the utilization of a well verified burnup code system. In this work a newly home-developed burnup code called BUCAL1 is presented. The code provides
B. El Bakkari, T. El Bardouni, B. Nacir, C. El Younoussi, Y. Boulaich, H. Boukhal   +5 more
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Comparison between codes MCNPX and Gate/Geant4 in volume fraction studies

Applied Radiation and Isotopes, 2020
Knowing the volume fraction in a multiphase flow is of fundamental importance in predicting the performance of many systems and processes, it has been possible to model an experimental apparatus for volume fraction studies using Monte Carlo codes. Artificial neural networks have been applied for the recognition of the pulse height distributions in ...
Renato Raoni Werneck Affonso, Caroline Mattos Barbosa, Roos S.F. Dam, William L. Salgado, Ademir X. da Silva, César M. Salgado   +5 more
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Prediction of 67Ga production using the Monte Carlo code MCNPX

Applied Radiation and Isotopes, 2013
The widely used Monte Carlo simulation code Monte Carlo N-Particle System (MCNPX) has been utilized to simulate the production of (67)Gallium via multiple nuclear reaction channels. Based on the MCNPX-generated, energy-dependent proton flux within a Zn target during irradiation, the (67)Ga production yield was determined.
M, Sadeghi, N, Jokar, T, Kakavand, H, Ghafoori Fard, C, Tenreiro   +4 more
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Computed radiography simulation using the Monte Carlo code MCNPX

Applied Radiation and Isotopes, 2010
Simulating X-ray images has been of great interest in recent years as it makes possible an analysis of how X-ray images are affected owing to relevant operating parameters. In this paper, a procedure for simulating computed radiographic images using the Monte Carlo code MCNPX is proposed.
S C A, Correa, E M, Souza, A X, Silva, D H, Cassiano, R T, Lopes   +4 more
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SOFT-RT: Software for IMRT simulations based on MCNPx code

Applied Radiation and Isotopes, 2016
Intensity Modulated Radiation Therapy (IMRT) is an advanced treatment technique, widely used in external radiotherapy. This paper presents the SOFT-RT which allows the simulation of an entire IMRT treatment protocol. The SOFT-RT performs a full three-dimensional renderization of a set of patient images, including the definitions of region of interest ...
Telma Cristina Ferreira, Fonseca, Tarcisio Passos Ribeiro, Campos   +1 more
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