Results 1 to 10 of about 10,040 (154)
Neutronic Evaluation of MSBR System Using MCNP Code
Brazilian Journal of Radiation Sciences, 2021 The concept of Molten Salt Reactor use Th to breed fissile 233U, where an initial source of fissile material needs to be provided. However, there is no available 233U and so; the fissile fuel supply is one of the unresolved problems.
Clarysson Alberto Mello da Silva +3 more
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The MCNP®6 code: A decade of progress
EPJ Nuclear Sciences & TechnologiesAfter 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
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SIMULATION OF XRF SPECTRA EMPLOYING A MODIFIED MCNP CODE
Tạp chí Khoa học Đại học Đà Lạt, 2021 The Monte Carlo N-Particle code (MCNP4C2 version) has been modified for atomic relaxation in both source code and library to simulate XRF spectra for different measurement configurations.
Nguyen Thi Tho +2 more
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k0-PGNAA of pollutants in aqueous samples using MCNP code [PDF]
Ядерна фізика та енергетика, 2014 Prompt γ-neutron activation analysis (PGNAA) using the k0 method by employing the 1951.1 keV γ-line of the 35Cl(n, γ)36Cl thermal neutron reaction as monostandard comparator was described.
A. Hamid, Hesham Shahbunder
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Study of bremsstrahlung photons in bulk target using MCNP code [PDF]
Ядерна фізика та енергетика, 2017 The aim of this research was to study the feasibility of bremsstrahlung photon production in target bombarded by 1 GeV electrons. The calculations were performed by the Monte Carlo code MCNP.
S. Sangaroon, W. Tuisakda
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SCIENTIFIC WORKFLOWS FOR MCNP6 AND PROTEUS WITHIN THE NEAMS WORKBENCH [PDF]
EPJ Web of Conferences, 2021 In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling and Simulation (NEAMS)Workbench.
Dominesey Kurt A. +3 more
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A Monte Carlo Platform for Characterization of X-Ray Radiation Dose in CT Imaging [PDF]
Journal of Biomedical Physics and Engineering, 2021 Background: Computed tomography (CT) is currently known as a versatile imaging tool in the clinic used for almost all types of cancers. The major issue of CT is the health risk, belonging to X-ray radiation exposure.
Delaram Pakravan +4 more
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Predicting Ex-core Detector Response in a PWR with Monte Carlo Neutron Transport Methods [PDF]
EPJ Web of Conferences, 2020 An approach for calculating ex-core detector response using Monte Carlo code MCNP was developed. As a first step towards ex-core detector response prediction a detailed MCNP model of the reactor core was made.
Goričanec Tanja +4 more
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csg2csg: A TOOL TO ASSIST VALIDATION & VERIFICATION [PDF]
EPJ Web of Conferences, 2021 The csg2csg tool is a minimal dependency Python3 based program to facilitate the comparison of radiation transport Monte Carlo codes. The csg2csg can currently parse MCNP and OpenMC geometry descriptions, and it can subsequently export MCNP, FLUKA, PHITS,
Davis Andrew +2 more
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Validation of MCS code for shielding calculation using SINBAD
Nuclear Engineering and Technology, 2022 The MCS code is a computer code developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation and calculation of nuclear reactor systems based on the Monte Carlo method.
XiaoYong Feng +4 more
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