Dosimetric evaluation and Monte Carlo simulation of a new proposed surface brachytherapy mould. [PDF]
J Contemp BrachytherapySalamat F +4 more
europepmc +1 more source
Physico-mechanical characterization and gamma radiation shielding capability of granodiorite from Suwayqat El-Arsha, Egypt; implications for construction and natural radiation shielding. [PDF]
Sci RepAzer MK +4 more
europepmc +1 more source
Recent Advances and Challenges in Polymer-Based Materials for Space Radiation Shielding. [PDF]
Polymers (Basel)Toto E +3 more
europepmc +1 more source
Experimental and simulation study of shielding features of polyester/HgO composites against photons using GEANT4 and MCNP codes. [PDF]
Sci RepZebardast V, Saray AA.
europepmc +1 more source
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MCNPX-PoliMi for nuclear nonproliferation applications
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2012This 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 +11 more
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Delayed-Gamma Simulation Using MCNPX
Nuclear Technology, 2009Monitoring 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 +4 more
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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 +4 more
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Simulation of neutron production using MCNPX+MCUNED
Radiation Protection Dosimetry, 2013In 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
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Simulation of phoswich detectors using MCNPX and EGSNRC
Radiation Protection Dosimetry, 2010The 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.
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Monte-Carlo Simulations: FLUKA vs. MCNPX
AIP Conference Proceedings, 2007Several 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 +7 more
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