Results 171 to 180 of about 6,588 (195)

Correlated gammas using CGM and MCNPX

Progress in Nuclear Energy, 2013
Abstract Transport codes like MCNPX (Monte Carlo N-Particle eXtended) which are based primarily on experimentally derived data libraries at energies below approximately 100 MeV are reliable and predictive in transporting and producing neutrons and gammas.
Trevor Wilcox, Toshihiko Kawano, Gregg W. McKinney, John S. Hendricks   +3 more
openaire   +1 more source

An antiproton simulation study using MCNPX for radiation therapy

Journal of X-Ray Science and Technology: Clinical Applications of Diagnosis and Therapeutics, 2011
Radiation therapy using antiprotons is a potential interesting future modality. Energetic antiprotons penetrate matter with almost near identical stopping powers and radio biological effectiveness (RBE) as protons in the region well before the Bragg peak region.
Stephen, Michael Handley, Salahuddin, Ahmad   +1 more
openaire   +2 more sources

Non-static surfaces in MCNPX: The chopper extension1

Journal of Neutron Research, 2020
Rotating objects, such as choppers, are common components of a neutron beamline, and the motion of these components is not described in the static geometry of an MCNPX model. The special case of non-static surfaces for rotation about a stationary point in space has been developed for MCNPX.
Grammer, Kyle B., Gallmeier, Franz X., Iverson, Erik B.   +2 more
openaire   +2 more sources

Full core analysis of IRIS reactor by using MCNPX

Applied Radiation and Isotopes, 2016
This paper describes neutronic analysis for fresh fuelled IRIS (International Reactor Innovative and Secure) reactor by MCNPX code. The analysis included criticality calculations, radial power and axial power distribution, nuclear peaking factor and axial offset percent at the beginning of fuel cycle.
E A, Amin, I I, Bashter, Nabil M, Hassan, S S, Mustafa   +3 more
openaire   +2 more sources

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
openaire   +2 more sources

Quantitative comparison between PGNAA measurements and MCNPX simulations

Journal of Radioanalytical and Nuclear Chemistry, 2015
A MCNPX model of a neutron activation facility for radioactive waste characterization was built to support experimental studies. To validate this model, small samples of different elemental composition were irradiated and experimental data are compared to simulation results obtained using different neutron capture prompt gamma ray databases.
Nicol, T., Carasco, C., Perot, B., Ma, J. L., Payan, E., Mauerhofer, E., Havenith, A., Collot, J.   +7 more
openaire   +2 more sources

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
openaire   +1 more source

MCNPX vs. DORT for sns shielding design studies

Radiation Protection Dosimetry, 2005
Radiation transport occurs through the 18 m long access way adjacent to the Spallation Neutron Source accelerator tunnel and the 2.2 m thick massive shielding door which closes the access way. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for construction of the door to study radiation penetration.
openaire   +2 more sources

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
openaire   +2 more sources

A new implementation of scattering kernels in MCNPX

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2004
Abstract With the increased demand for cold neutrons the designers of cold sources are challenged to improve the quality of theoretical predictions of the behavior of such sources. This challenge can be met by improving codes like MCNPX or by improving the physics behind the codes. This paper discusses the impact improving the code has on the results
G Muhrer, A Stupnik, E Schachinger
openaire   +1 more source