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Gemma: Development of a two-dimensional neutron transport code with the method of characteristics
Annals of Nuclear Energy, 2018Abstract This work describes the development of Gemma code, a next generation neutron transport solver capable of employing accurate solution methods with the ability to incorporating the latest computing techniques and providing a flexible developmental environment.
Guillermo Ibarra +1 more
exaly +2 more sources
Development and preliminary verification of a Monte Carlo neutron transport code IMPC-Neutron
Annals of Nuclear Energy, 2022Yongwei Yang
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The Application of Neutron Transport Codes to the Transport of Neutrals in Plasmas
Nuclear Science and Engineering, 1976The application of the linear Boltzmann equation as used in reactor and shielding problems to the transport of neutral atoms in a Tokamak-type plasma has been studied. The method was found to be generally valid with some limitations because of possible anisotropy of the plasma medium.
J. H. Marable, E. M. Oblow
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Three Dose Calculation Codes Applied to Neutron Transport in BNCT
2001The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP ...
Lampinen, Juha +3 more
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Benchmarking of Neutron Production of Heavy-Ion Transport Codes
Journal of ASTM International, 2012Abstract Accurate prediction of radiation fields generated by heavy ion interactions is important in medical applications, space missions, and in design and operation of rare isotope research facilities. In recent years, several well-established computer codes in widespread use for particle and radiation transport calculations have been ...
I. Remec, R. M. Ronningen, L. Heilbronn
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A comparison of two neutron transport codes
Annals of Nuclear Energy, 1981Abstract The flux distribution of 14 MeV neutrons inside an iron shield was calculated using two different transport codes, a discrete ordinates code (DOT) and a Monte Carlo code (MORSE). The two sets of results were found to be in good agreement for depths up to 60 cm and they agreed to within 40% of the DOT values for depths up to 120 cm.
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SFR mechanical scenarios and neutron transport transients with CAST3M code
Annals of Nuclear Energy, 2017Abstract In this paper we focus on of Sodium Fast Reactor core undergoing several mechanical scenarios. The mechanical full-core model in Cast3M code is described using finite elements method and Fluid-Structure Interaction is taken into account.
Kępisty, Grzegorz +3 more
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Recent validation study of a Method of Characteristics based Neutron Transport Code
Life Cycle Reliability and Safety Engineering, 2020We have reported the development of a computer code based on Method of Characteristics (MOC) to solve neutron transport equation for mainly lattice (i.e. assembly) level calculations with reflective and periodic boundary conditions and to some extent, core level calculation with vacuum boundary condition.
Tanay Mazumdar, Tej Singh
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TRIPOLI-3: A Neutron/Photon Monte Carlo Transport Code
2001The present version of TRIPOLI-3 [1-3] solves the transport equation for coupled neutron and gamma ray problems in three dimensional geometries by using the Monte Carlo method. This code is devoted both to shielding and criticality problems. The most important feature for particle transport equation solving is the fine treatment of the physical ...
J. C. Nimal, T. Vergnaud
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Experimental Validation of Neutron Spectra Calculated via Transport Codes
1985The results of discrete ordinate DOT calculations are compared with Multiple Foil Activation measurements performed at RB-2/TV research facility (Montecuccolino Laboratories, Bologna) and at Caorso power plant (Caorso, Piacenza).
E. Borioli +4 more
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