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Radiat Prot Dosimetry. 2016 Sep;170(1-4):350-3. doi: 10.1093/rpd/ncv379. Epub 2015 Aug 13.

MCNP SIMULATION OF THE HP(10) ENERGY RESPONSE OF A BRAZILIAN TLD ALBEDO NEUTRON INDIVIDUAL DOSEMETER, FROM THERMAL TO 20 MeV.

Author information

1
Coordenação dos Programas de Pós Graduação em Engenharia, COPPE/PEN, CEP: 21941-972, Rio de Janeiro, RJ, Brazil Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, s/n, Recreio, CEP: 22783-127, Rio de Janeiro, RJ, Brazil bfreitas@con.ufrj.br.
2
Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, s/n, Recreio, CEP: 22783-127, Rio de Janeiro, RJ, Brazil.
3
Coordenação dos Programas de Pós Graduação em Engenharia, COPPE/PEN, CEP: 21941-972, Rio de Janeiro, RJ, Brazil.

Abstract

The Brazilian Instituto de Radioproteção e Dosimetria (IRD) runs a neutron individual monitoring system with a home-made TLD albedo dosemeter. It has already been characterised and calibrated in some reference fields. However, the complete energy response of this dosemeter is not known, and the calibration factors for all monitored workplace neutron fields are difficult to be obtained experimentally. Therefore, to overcome such difficulties, Monte Carlo simulations have been used. This paper describes the simulation of the HP(10) neutron response of the IRD TLD albedo dosemeter using the MCNPX transport code, for energies from thermal to 20 MeV. The validation of the MCNPX modelling is done comparing the simulated results with the experimental measurements for ISO standard neutron fields of (241)Am-Be, (252)Cf, (241)Am-B and (252)Cf(D2O) and also for (241)Am-Be source moderated with paraffin and silicone. Bare (252)Cf are used for normalisation.

PMID:
26276807
DOI:
10.1093/rpd/ncv379
[Indexed for MEDLINE]

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