Monte Carlo simulations and dosimetric studies of an irradiation facility

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Volumn 580, Issue 1 SPEC. ISS., 2007, Pages 70-72

  Belchior, A ^a   Botelho, M L ^a   Vaz, P ^a  

^a INSTITUTO TECNOLÓGICO E NUCLEAR   (Portugal)

Author keywords

Cobalt 60 gamma irradiator; Dose mapping; Fricke solution; MCNPX code

Indexed keywords

COMPUTER SIMULATION; DOSIMETRY; ELECTRON IRRADIATION; IONIZING RADIATION; PROTON IRRADIATION; ROBOTICS;

COBALT 60 GAMMA IRRADIATORS; DOSE MAPPING; FRICKE SOLUTION; MCNPX CODE;

MONTE CARLO METHODS;

EID: 34548212480     PISSN: 01689002     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nima.2007.05.040     Document Type: Article

References (2)

1. Oliveira C., and Salgado J. Isodose distributions and dose uniformity in the Portuguese gamma irradiation facility calculated using the MCNP code. Radiat. Phys. Chem. 61 3-6 (2001) 791-793
2. ICRU, Radiation Dosimetry: X-rays and Gamma Rays with Maximum Photon Energies Between 0.6 and 50 MeV, ICRU Report 14 (Bethesda, Maryland: International Commission on Radiation Units and Measurements), 1969.