Neutron spectra re-binning and dose calculation using Monte Carlo methods

One hundred thirty lethargy neutron spectra in 60 energy groups were converted to energy spectra and re-binned to 31 energy groups. Originalspectra were taken form the compilation published by the IAEA and covers neutron spectra from isotopic neutron sources, nuclear reactors,medical and physical ap...

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Detalles Bibliográficos
Autores: J.M. Ortiz Rodríguez, T. Arteaga Arteaga, H. R. Vega-Carrillo, E. Manzanares Acuña
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2007
País:México
Institución:Universidad Autónoma de Zacatecas
Repositorio:Redalyc-UAZ
OAI Identifier:oai:redalyc.org:57066302
Acceso en línea:https://www.redalyc.org/articulo.oa?id=57066302
https://www.redalyc.org/journal/570/57066302/
https://www.redalyc.org/journal/570/57066302/html/
https://www.redalyc.org/journal/570/57066302/57066302.epub
https://www.redalyc.org/journal/570/57066302/movil
Access Level:acceso abierto
Palabra clave:Física, Astronomía y Matemáticas
dose
Monte Carlo
Neutron spectrometry
Descripción
Sumario:One hundred thirty lethargy neutron spectra in 60 energy groups were converted to energy spectra and re-binned to 31 energy groups. Originalspectra were taken form the compilation published by the IAEA and covers neutron spectra from isotopic neutron sources, nuclear reactors,medical and physical application accelerators, cosmic rays, etc. The 31 energy groups were taken from the BUNKIUT unfolding code, whichis utilized to obtain the neutron spectrum from a multisphere neutron spectrometer. Re-binned spectra were utilized to calculate the ambient,personal and effective doses covering 13 types of doses. This calculation was carried out through the ICRP74 dose-to-fluence conversioncoefficients. This procedure was performed using Monte Carlo methods using the MCNP 4C code. Two experiments were carried out toobtain, with a Bonner sphere spectrometer, the BUNKIUT code and the UTA4 response matrix, the neutron spectra of 252Cf and 252Cf/D2O.For both sources and at the same locations the equivalent ambient dose were measured using a rem meter. Measured H*(10) and neutronspectra were compared with those obtained in the Monte Carlo calculations.