Published October 2016 | Version v1
Miscellaneous Open

A 222 energy bins response matrix for a 6Lil scintillator Bss system

  • 1. Centro de Desenvolvimento da Tecnologia Nuclear, Laboratorio de Calibracao de Dosimetros, Av. Pte. Antonio Carlos 6627, 31270-901 Pampulha, Belo Horizonte, Minas Gerais (Brazil)
  • 2. Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico)
  • 3. Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Laboratorio de Patrones Neutronicos, Av. Complutense 22, 28040 Madrid (Spain)
  • 4. Universidad Politecnica de Madrid, Departamento de Ingenieria Nuclear, 28006 Madrid (Spain)

Description

A new response matrix was calculated for a Bonner Sphere Spectrometer (Bss) with a 6Lil(Eu) scintillator. We utilized the Monte Carlo N-particle radiation transport code MCNPX, version 2.7.0, with Endf/B-VII.0 nuclear data library to calculate the responses for 6 spheres and the bare detector, for energies varying from 9.441 E(-10) MeV to 105.9 MeV, with 20 equal-log(E)-width bins per energy decade, totalizing 222 energy groups. A Bss, like the modeled in this work, was utilized to measure the neutron spectrum generated by the 241AmBe source of the Universidad Politecnica de Madrid. From the count rates obtained with this Bss system we unfolded neutron spectrum utilizing the BUNKIUT code for 31 energy bins (UTA-4 response matrix) and the MAXED code with the new calculated response functions. We compared spectra obtained with these Bss system / unfold codes with that obtained from measurements performed with a Bss system constituted of 12 spheres with a spherical 3He Sp-9 counter (Centronic Ltd., UK) and MAXED code with the system-specific response functions (Bss-CIEMAT). A relatively good agreement was observed between our response matrix and that calculated by other authors. In general, we observed an improvement in the agreement as the energy increases. However, higher discrepancies were observed for energies close to 1-E(-8) MeV and, mainly, for energies above 20 MeV. These discrepancies were mainly attributed to the differences in cross-section libraries employed. The ambient dose equivalent (H (10)) calculated with the 6Lil-MAXED showed a good agreement with values measured with the neutron area monitor Bert hold Lb 6411 and within 12% the value obtained with another Bss system (Bss-CIEMAT). The response matrix calculated in this work can be utilized together with the MAXED code to generate neutron spectra with a good energy resolution up to 20 MeV. Some additional tests are being done to validate this response matrix and improve the results for energies higher than 20 MeV. (Author)

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Additional details

Publishing Information

Publisher
Sociedad Mexicana de Irradiacion y Dosimetria
Imprint Place
Ciudad de Mexico (Mexico)
Imprint Pagination
23 p.
Report number
INIS-MX--3053

Conference

Title
16. International Symposium on Solid State Dosimetry
Original Conference Title
16. Simposio Internacional de Dosimetria de Estado Solido
Dates
24-28 Sep 2016
Place
Tuxtla Gutierrez, Chiapas (Mexico)