CR 39 detector efficiency estimation a neutron emitted by an isotopic source to application in neutron dosimetry

Bertin Pérez, Bedher Vega-Cabrera

Producción científica: Capítulo del libro/informe/acta de congresoContribución a la conferenciarevisión exhaustiva


Solid-state nuclear trace detectors, such as the Cr-39 (PADC), are used in neutron dosimetry. By placing a converter like SN1 sheet (natural boron + polyester) on the surface of the trace detector, it can record alpha particles that come from the nuclear reaction (n, α). For this, a program based on Monte Carlo simulations was developed to estimate the efficiency of the detector to neutrons emitted from a 241Am-Be isotopic source. The program uses the code MCNP6.1.0 to calculate the rate of reactions ( produced in the sheet of natural boron. The results of MCNP6.1.0 were manipulated by means of a sub-routine written in Python, generating a volumetric arrangement of 5 x 5 x 10 in natural boron. The subroutine determines which alpha particles from natural boron are capable of producing visible traces on the detector.
Idioma originalEspañol
Título de la publicación alojadaISSSD 2020
Número de páginas19
EstadoPublicada - 1 ene. 2020

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