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Gamma radiation with energies greater than 1.25 MeV are usually produced in reactor enviroim[ients, particle accelerators and in cosmic radiation fields. For these energies, the response of a dosimeter heavily vary with the absorber material thickness, up to attain a maximum value named as charged particle equilibrium thickness. The main gol of this paper was the experimental determination of the absorbed dose profile in an aluminum sample for several energies of gamma ray beam, in order to obtain a relationship between the average energy of the gamma radiation field and the charged particle equilibrium thickness. The dosimeters were irradiated with gamma radiation produced by thermal neutron capture in 23 target materials in the experimental arrangement mounted at the tangential beam hole of the BPEN-CNEN/SP reactor. For the determination of the charged particle equilibrium thickness, it was fitted to the experimental data a semi-empirical fimction which allowed to obtain the thickness of CTPE ( Charged Particle Transient Equilibrium ) for each gamma radiation spectrum used in this work, with average energy varying in the interval from 3.26 to 7.85 MeV. The experimental results of the present paper allowed to obtain a relationship between average energy of the radiation field and the CTPE thickness, which presents an excellent agreement with the corrected range for electrons produced in that energy.

Medida do Perfil de Dose no Alumínio Irradiado com Raios Gama de Captura de Nêutrons Térmicos Utilizando o Dosímetro Termoluminescente CaSO4:Dy