Results 11 to 20 of about 8,745 (215)
, 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 ...
Stevens, J. G. +1 more
core +4 more sources
MCNP certification package [PDF]
, 1992 In response to a Department of Energy (DOE) request, Westinghouse Savannah River Company committed to certify all computer codes used in critical calculations at the site. Since the Monte Carlo Neutron Photon Transport (MCNP) code will be used to perform
Trumble, E. F.
core +3 more sources
Potential MCNP enhancements for NCT [PDF]
, 1992 MCNP a 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.
William M. Taylor +3 more
core +5 more sources
MCNP-GO: A Python package for assembling MCNP input files with a systems engineering approach
Nuclear Engineering and TechnologyThis article introduces MCNP-GO (https://github.com/afriou/mcnpgo), an open-source 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 ...
A. Friou
doaj +3 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.
Cardon, D. A. +7 more
core +4 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 +3 more
doaj +3 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.
Wagner, J. C. +3 more
core +3 more sources
MCNP: Photon benchmark problems [PDF]
, 1991 The recent widespread, markedly increased use of radiation transport codes has produced greater user and institutional demand for assurance that such codes give correct results.
Whalen, Daniel J. +2 more
core +4 more sources
THE DOUNREAY FAST REACTOR VAULT CHARACTERISATION USING THE MONTE CARLO N-PARTICLE CODE AS A TOOL TO SUPPORT DECOMMISSIONING PLANNING [PDF]
EPJ Web of Conferences, 2021 A combined empirical and theoretical characterisation approach was taken in order to investigate the activity distribution and inventory in the Dounreay Fast Reactor (DFR) vault, so as to aid with the decommissioning and waste management strategy of the ...
Baldioli Vittoria +3 more
doaj +1 more source
CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2021 Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation.
Fausser Clément +18 more
doaj +1 more source