Results 11 to 20 of about 16,330 (259)

The REBUS-MCNP linkage. [PDF]

, 2009
The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup.
Stevens, J. G., Argonne National Laboratory. Nuclear Engineering Division.   +1 more
openaire   +3 more sources

Generation of 3D reference dosimetric datasets towards adoption of model-based dose calculations for permanent implant prostate brachytherapy. [PDF]

Med Phys
Abstract Purpose This work aims to create and validate a comprehensive set of test cases and 3D reference dosimetric datasets for model‐based dose calculation algorithms (MBDCAs) in permanent implant prostate brachytherapy. These test cases address the limits of the standard TG‐43 formalism towards improving dose evaluations in prostate cancer ...
Akbari F, Peppa V, Ouellet S, Moghadam N, Oliver S, Gimenez-Alventosa V, Beaulieu L, Vijande J, Thomson RM.   +8 more
europepmc   +2 more sources

Potential MCNP Enhancements for NCT [PDF]

, 1993
MCNP,1 a Los Alamos National Laboratory Monte Carlo radiation transport code, is currently widely used in the medical community for a variety of purposes including treatment planning, diagnostics, beam design, tomographic studies, and radiation protection.
Estes, G. P., Taylor, W. M.
core   +4 more sources

MCNP: Multigroup/adjoint capabilities [PDF]

, 1994
This report discusses various aspects related to the use and validity of the general purpose Monte Carlo code MCNP for multigroup/adjoint calculations. The increased desire to perform comparisons between Monte Carlo and deterministic codes, along with the ever-present desire to increase the efficiency of large MCNP calculations has produced a greater ...
Wagner, J. C., Redmond, E. L., II, Palmtag, S. P., Hendricks, J. S.   +3 more
openaire   +3 more sources

Clinical test cases for commissioning, QA, and benchmarking of model-based dose calculation algorithms in ¹⁹²Ir HDR gynecologic tandem and ring brachytherapy. [PDF]

Med Phys
Abstract Purpose To develop clinically relevant test cases for commissioning Model‐Based Dose Calculation Algorithms (MBDCAs) for 192Ir High Dose Rate (HDR) gynecologic brachytherapy following the workflow proposed by the TG‐186 report and the WGDCAB report 372.
Peppa V, Robitaille M, Akbari F, Enger SA, Thomson RM, Mourtada F, Fonseca GP.   +6 more
europepmc   +2 more sources

MCNP-GO: A Python package for assembling MCNP input files with a systems engineering approach

Nuclear Engineering and Technology
This article introduces MCNP-GO (https://github.com/afriou/mcnpgo), a Python package designed to manipulate and assemble MCNP input files, allowing users to assemble a set of independent objects, each described by a valid MCNP file, into a single cohesive file.
A. Friou
openaire   +4 more sources

ITER full model in MCNP for radiation safety demonstration. [PDF]

Nat Commun
The development of nuclear fusion as a safe and virtually limitless power source is receiving growing attention in the context of looming energy crisis and climate change.
Juarez R, Belotti M, Kolsek A, López V, Alguacil J, Pedroche G, López-Revelles AJ, Martínez-Albertos P, De Pietri M, Guijosa P, Le Tonqueze Y, Loughlin MJ, Polunovskiy E, Pampin R, Fabbri M, Sanz J.   +15 more
europepmc   +2 more sources

MCNP: Neutron benchmark problems [PDF]

, 1991
The recent widespread and increased use of radiation transport codes has produced greater user and institutional demand for assurances that such codes give correct results. Responding to these requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on criticality, pulsed sphere, and shielding neutron ...
Whalen, D. J., Cardon, D. A., Uhle, J. L., Hendricks, J. S.   +3 more
openaire   +3 more sources

Elaborate SMART MCNP Modelling Using ANSYS and Its Applications [PDF]

EPJ Web of Conferences, 2017
An MCNP 3-dimensional model can be widely used to evaluate various design parameters such as a core design or shielding design. Conventionally, a simplified 3-dimensional MCNP model is applied to calculate these parameters because of the cumbersomeness ...
Song Jaehoon, Surh Han-bum, Kim Seung-jin, Koo Bonsueng   +3 more
doaj   +3 more sources

<i>Vitess 3.8</i>: a modernized framework for Monte Carlo neutron tracing simulations. [PDF]

J Appl Crystallogr
VITESS 3.8 introduces modernized neutron‐source modeling with new artificial‐intelligence‐based and KDSource modules, plus expanded component support including a prism module and NCrystal‐integrated sample module. It also delivers major upgrades to existing modules and multiple new features, advancing the simulation framework.VITESS is a modular Monte ...
Robledo JI, Violini N, Beule F, Voigt J, Zakalek P, Lieutenant K.   +5 more
europepmc   +2 more sources