Results 131 to 140 of about 1,181 (179)

Preclinical in vivo dosimetry of healthy tissues in radiopharmaceutical therapy: implementation of a physiologically realistic mouse eye model in GATE. [PDF]

EJNMMI Res
Jouberton E, Sas N, Billoux T, Auzeloux P, Schmitt S, Mazuel L, Chezal JM, Miot-Noirault E, Ranchon-Cole I, Cachin F.   +9 more
europepmc   +1 more source

Interfacing MCNPX and McStas for simulation of neutron transport [PDF]

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2013
Abstract Simulations of target-moderator-reflector system at spallation sources are conventionally carried out using Monte Carlo codes such as MCNPX (Waters et al., 2007 [1] ) or FLUKA (Battistoni et al., 2007; Ferrari et al., 2005 [2] , [3] ) whereas simulations of neutron transport from the moderator and the instrument response are performed by ...
Franz X Gallmeier, Bent Lauritzen, Esben Bryndt Klinkby   +2 more
exaly   +2 more sources

Some of the next articles are maybe not open access.

Related searches:

MCNPX simulation of a multileaf collimator

Medical Physics, 2006
Our purpose in this work was to validate a very detailed Monte Carlo model, developed in MCNPX, of a Millennium 120 multileaf collimator integrated into a Varian Clinac 21EX treatment head. The Monte Carlo results were compared with measurements for both the and photon modes.
Falk, Pönisch, Uwe, Titt, Stephen F, Kry, Oleg N, Vassiliev, Radhe, Mohan   +4 more
openaire   +2 more sources

MCNPX-PoliMi for nuclear nonproliferation applications

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2012
This paper describes the use of the Monte Carlo code MCNPX-PoliMi for nuclear-nonproliferation applications, with particular emphasis on the simulation of spontaneous and neutron-induced nuclear fission. New models for the outgoing neutrons and gamma rays emitted in spontaneous and induced fission are described.
S. A. Pozzi, S. D. Clarke, W. Walsh, E. C. Miller, J. Dolan, M. Flaska, B. M. Wieger, A. Enqvist, PADOVANI, ENRICO, J. K. Mattingly, D. Chichester, P. Peerani   +11 more
openaire   +2 more sources

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.
Toshihiko Kawano, Trevor Wilcox, John S Hendricks   +2 more
exaly   +2 more sources

Simulation of phoswich detectors using MCNPX and EGSNRC

Radiation Protection Dosimetry, 2010
The in vivo monitoring Lab at KIT uses two phoswich detectors for routine lung counting. A simplified model of one of them has been implemented in the two Monte Carlo codes EGSnrc and MCNPX. The active part of the detector consists of a crystal of NaI(Tl) and one of CsI(Tl): the energy deposited in both the crystals have been studied to consider the ...
Leone, D., Breustedt, B.
openaire   +3 more sources

Simulation of neutron production using MCNPX+MCUNED

Radiation Protection Dosimetry, 2013
In standard MCNPX, the production of neutrons by ions cannot be modelled efficiently. The MCUNED patch applied to MCNPX 2.7.0 allows to model the production of neutrons by light ions down to energies of a few kiloelectron volts. This is crucial for the simulation of neutron reference fields.
M, Erhard, P, Sauvan, R, Nolte
openaire   +2 more sources

Delayed-Gamma Simulation Using MCNPX

Nuclear Technology, 2009
Monitoring issues related to activation and fission processes occur in many health physics, instrumentation and equipment design, nuclear forensics, and homeland security applications. Gamma radiation that is emitted during these processes as a result of the radioactive decay of reaction by-products [delayed gammas (DGs)] provides unique signatures ...
Joe W. Durkee, Gregg W. McKinney, Holly R. Trellue, Laurie S. Waters, William B. Wilson   +4 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