MCNP SIMULATION OF THE HP(10) ENERGY RESPONSE OF A BRAZILIAN TLD ALBEDO NEUTRON INDIVIDUAL DOSEMETER, FROM THERMAL TO 20 MeV.
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.
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.
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Freitas
Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, s/n, Recreio, CEP: 22783-127, Rio de Janeiro, RJ, Brazil.
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Martins
Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, s/n, Recreio, CEP: 22783-127, Rio de Janeiro, RJ, Brazil.
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Pereira
Coordenação dos Programas de Pós Graduação em Engenharia, COPPE/PEN, CEP: 21941-972, Rio de Janeiro, RJ, Brazil.
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da Silva
Instituto de Radioproteção e Dosimetria, Av. Salvador Allende, s/n, Recreio, CEP: 22783-127, Rio de Janeiro, RJ, Brazil.
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Mauricio
D000465:Algorithms; D000576:Americium / Q000032:analysis; D001608:Beryllium / Q000032:analysis; D001895:Boron / Q000032:analysis; D001938:Brazil; D002138:Calibration; D002142:Californium / Q000032:analysis; D003198:Computer Simulation; D006801:Humans; D008422:Materials Testing; D009010:Monte Carlo Method; D009502:Neutrons; D016273:Occupational Exposure / Q000032:analysis; D010232:Paraffin / Q000737:chemistry; D011829:Radiation Dosage; D000072232:Radiation Dosimeters; D011834:Radiation Monitoring / Q000295:instrumentation* / Q000379:methods; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D012680:Sensitivity and Specificity; D012825:Silicon / Q000737:chemistry; D012984:Software; D013819:Thermoluminescent Dosimetry / Q000379:methods*
D010232:Paraffin; D002142:Californium; D001895:Boron; D001608:Beryllium; D000576:Americium; D012825:Silicon