Results 141 to 150 of about 1,181 (179)

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

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

Modeling the thermoluminescent response of CaSO4:Dy by the MCNPX method

Applied Radiation and Isotopes, 2010
This work describes an algorithm for absorbed dose evaluation in the region of X-ray diagnostic energy based on the response of CaSO(4):Dy thermoluminescence powder detectors. The absorbed dose was calculated using Monte Carlo simulation code (MCSC) and then compared to the experimental TLD results for X-rays effective energies (60)Co gamma radiation ...
C, Furetta, J, Roman, T, Rivera, J, Azorín, C G, Azorín, H R, Vega-Carrillo   +5 more
openaire   +2 more sources

The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

Nuclear Technology, 2010
Monte Carlo–linked depletion methods have gained recent interest due to the ability to model complex three-dimensional geometries using continuous-energy cross sections.
Michael L. Fensin, John S. Hendricks, Samim Anghaie   +2 more
openaire   +1 more source

Development of the MCNPX model for the portable HPGe detector

Radiation Physics and Chemistry, 2014
The portable HPGe coaxial detector Canberra Big MAC is used in LVR-15 research reactor for spectrometric measurement of spent nuclear fuel. The fuel is measured in the dedicated system located in the spent fuel pool situated near the reactor. For the purpose of the spectrometric system calibration, the detector was precisely modeled with the MCNPX code.
Michal Koleska, Ladislav Viererbl, Milan Marek   +2 more
openaire   +1 more source

GEANT4 benchmark with MCNPX and PHITS for activation of concrete

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2018
Abstract The activation of concrete is a real problem from the point of view of waste management. Because of the complexity of the issue, Monte Carlo (MC) codes have become an essential tool to its study. But various codes or even nuclear models exist in MC.
Robin Tesse, Frédéric Stichelbaut, Nicolas Pauly, Alain Dubus, Jonathan Derrien   +4 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

Proton Therapy of eye using MCNPX code

2018
Introduction: Proton radiotherapy is the one of advanced teletherapy methods. The protons deposit their maximum energy in a position called Bragg peak. Therefore, for treatment of cancer, the tumor should be placed at the Bragg peak or SOBP. The scattered photons and neutrons is a challenge in proton radiotherapy.
Safaiean, S., Salehi Barough, M., Shirmardi, S.P.   +2 more
openaire   +1 more source

Monte-Carlo Simulations: FLUKA vs. MCNPX

AIP Conference Proceedings, 2007
Several experiments were performed at the Phasotron and Nuclotron accelerators in JINR Dubna in which spallation reactions and neutron transport were studied. The experimental results were checked against the predictions of the Monte‐Carlo code MCNPX.
M. Oden, A. Krasa, M. Majerle, O. Svoboda, V. Wagner, Carlos Granja, Claude Leroy, Ivan Stekl   +7 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.
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