Results 11 to 20 of about 10,040 (154)
Nuclear Engineering and Technology, 2017 In this work, linear and mass attenuation coefficients, effective atomic number and electron density, mean free paths, and half value layer and 10th value layer values of barium–bismuth–borosilicate glasses were obtained for 662 keV, 1,173 keV, and 1,332
Reza Bagheri +2 more
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Introduction to the Monte Carlo dose engine COMPASS for BNCT
Scientific Reports, 2023 The Monte Carlo method is the most commonly used dose calculation method in the field of boron neutron capture therapy (BNCT). General-purpose Monte Carlo (MC) code (e.g., MCNP) has been used in most treatment planning systems (TPS) to calculate dose ...
Wan-Bing Zhong +3 more
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A TOPOLOGY OPTIMIZATION PROCEDURE FOR ASSISTING THE DESIGN OF NUCLEAR COMPONENTS [PDF]
EPJ Web of Conferences, 2021 In this paper, we show that a module implemented in the MCNP transport code to perform sensitivity analyses can be diverted to perform topology optimizations of nuclear equipment.
Chabod Sébastien
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MCNP visual editor computer code manual [PDF]
, 1995 This document contains the manual for using the Monte Carlo N-Particle (MCNP) Visual Editor.
Carter, L. L., Schwarz, R. A.
openaire +2 more sources
Contributon Monte Carlo. [Application in MCNP code] [PDF]
, 1979 The contributon Monte Carlo method is based on a new recipe to calculate target responses by means of volume integral of the contributon current in a region between the source and the detector. A comprehensive description of the method, its implementation in the general-purpose MCNP code, and results of the method for realistic nonhomogeneous, energy ...
Dubi, A., Gerstl, S.A.W.
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An automated weight window generator based on the recursive Monte-Carlo method for use in MC shielding calculations [PDF]
EPJ Web of ConferencesMCNP code provides numerous variance reduction techniques that are mainly used to optimize the analog Monte Carlo simulations. These techniques can reduce the statistical uncertainty of the simulation results while minimizing computational costs.
Yadav Pratibha +3 more
doaj +1 more source
Monte Carlo Particle Lists: MCPL [PDF]
, 2017 A binary format with lists of particle state information, for interchanging particles between various Monte Carlo simulation applications, is presented.
Cai, Xiao Xiao +5 more
core +2 more sources
Radiation Safety Information Computational Center (RSICC): An Information Analysis Center for Nuclear Science [PDF]
EPJ Web of ConferencesThe Radiation Safety Information Computational Center (RSICC), founded in 1962 at Oak Ridge National Laboratory (ORNL), is a specialized information analysis center under the auspices of the Office of Science and Technical Information within the U.S ...
Valentine Timothy
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Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]
EPJ Web of Conferences, 2020 The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator).
Kos Bor +8 more
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Evaluation of RAPID for a UNF cask benchmark problem
EPJ Web of Conferences, 2017 This paper examines the accuracy and performance of the RAPID (Real-time Analysis for Particle transport and In-situ Detection) code system for the simulation of a used nuclear fuel (UNF) cask.
Mascolino Valerio +2 more
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