Results 81 to 90 of about 1,341 (152)
During heavy ion irradiation therapy the patient has to be located exactly at the right position to make sure that the Bragg peak occurs in the tumour. The patient has to be moved in the range of millimetres to scan the ill tissue.
Lapins Janis +3 more
doaj +1 more source
The MCNP®6 code: A decade of progress
After several years of effort involved in merging the Los Alamos National Laboratory MCNP5 and MCNPX codes, in 2013 the first production release of version 6 of the Monte Carlo N-Particle®, or MCNP®, code MCNP6.1 was distributed publicly.
Rising Michael E. +19 more
doaj +1 more source
Design and validation of shielding for a neutron generator using MCNP6
This study presents the design, fabrication, and experimental validation of a shielding facility for the DD-108 neutron generator installed for active neutron interrogation applications such as differential die-away analysis.
Jae Chang Kim +4 more
doaj +1 more source
Fast-neutron-induced fission of 242Pu at nELBE
The fast neutron-induced fission cross section of 242Pu was determined in the range of 0.5 MeV to 10 MeV relative to 235U(n,f) at the neutron time-of-flight facility nELBE.
Kögler Toni +10 more
doaj +1 more source
In this study, the multi-threading performance of the Geant4, MCNP6, and PHITS codes was evaluated as a function of the number of threads (N) and the complexity of the tetrahedral-mesh phantom.
김찬형
core +1 more source
Estudio de la respuesta de un TLD100-HARSHAW mediante el código de Monte Carlo MCNP6 [PDF]
[ES] El código MCNP6 se ha utilizado para desarrollar un modelo de Monte Carlo del TLD100- HARSHAW, incluyendo una fuente colimada y un fantoma de agua con paredes de PMMA (ISO water slab phantom).
Martorell Alsina, Sebastián Salvador +3 more
core
Modeling Eye Lens and Its Conversion Coefficients Using MCNP6
M.S.Recent studies have found the lens of the human eye to be more radiosensitive than previously thought with a questionable threshold dose for cataractogenesis.
Niemisto, Matti Guenter
core
Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations
In the solution of the neutron transport equation, the k-effective eigenvalue is related to the average number of neutrons emitted in fission of the system. It can be shown that if the average number of neutrons emitted in fission and the average neutron
Ortega, Mario Ivan
core
PurposeTo determine organ doses from a proton gantry-mounted cone-beam computed tomography (CBCT) system using two Monte Carlo codes and to study the influence on organ doses from different acquisition modes and repeated imaging.MethodsThe CBCT system ...
Henry, Thomas +7 more
core +1 more source
Monte Carlo simulation of neutron interaction in Mn bath used for primary standard neutron dosimetry
Ionizing Radiation Metrology Laboratory (IRML), National Institute of Standards (NIS), Egypt is developing its capabilities in neutron metrology to the primary standard level. Recently, a Mn-bath system was installed at IRML.
Khaled Mostafa +5 more
doaj +1 more source

