On a comparison of a neutron Monte Carlo transport simulation to a criticality benchmark experiment

Author:

Chaves Barcellos Luiz F.F.ORCID,Bodmann Bardo E.J.,Vilhena Marco T.M.B.

Funder

Coordenação de Aperfeiçoamento de Pessoal de Nível Superior

Conselho Nacional de Desenvolvimento Científico e Tecnológico

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference27 articles.

1. Barcellos, LuizFelipe F.C., Bodmann, Bardo E.J., Leite, SérgioQ. Bogado, de Vilhena, Marco T., 2015. A Monte Carlo simulation of a simplified reactor by decomposition of the neutron spectrum into fission, intermediate and thermal distributions. In: International Nuclear Atlantic Conference 2015.

2. On a continuous energy Monte Carlo simulator for neutron transport: Optimisation with fission, intermediate and thermal distributions;Barcellos,2017

3. Barcellos, LuizFelipe F.C., Bodmann, Bardo E.J., Leite, SérgioQ. Bogado, de Vilhena, Marco T., 2017b. A continuous energy neutron transport Monte Carlo simulator project: Decomposition of the neutron energy spectrum by target nuclei tagging. In: International Nuclear Atlantic Conference 2017.

4. Barcellos, LuizFelipe F.C., Bodmann, Bardo E.J., Leite, SérgioQ. Bogado, de Vilhena, Marco T., 2019. On a continuous Monte Carlo simulator project: Neutron shielding simulation. In: International Nuclear Atlantic Conference 2019.

5. On a Parametric Representation of the Angular Neutron Flux in the Energy Range from 1 eV to 10 MeV;Barcellos,2020

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4. Improvement of moderation efficiency for neutron source system in compact neutron radiography device;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2021-11

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