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- Title
MCNP SIMULATION OF THE H<sub>P</sub>(10) ENERGY RESPONSE OFA BRAZILIAN TLD ALBEDO NEUTRON INDIVIDUAL DOSEMETER, FROM THERMALTO 20MEV.
- Authors
Freitas, B. M.; Martins, M. M.; Pereira, W. W.; da Silva, A. X.; Mauricio, C. L. P.
- 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 241Am-Be, 252Cf, 241Am-B and 252Cf(D2O) and also for 241Am-Be source moderated with paraffin and silicone. Bare 252Cf are used for normalisation.
- Subjects
DOSIMETERS; NUCLEAR counters calibration; RADIATION dosimetry; MONTE Carlo method dose calculation; RADIATION protection; RADIATION exposure
- Publication
Radiation Protection Dosimetry, 2016, Vol 170, Issue 1-4, p350
- ISSN
0144-8420
- Publication type
Article
- DOI
10.1093/rpd/ncv379