Author/Authors :
Smetanin، نويسنده , , M. and Vasilenko، نويسنده , , Anton E. and Semenov، نويسنده , , M. and Takoudis، نويسنده , , G. and Xanthos، نويسنده , , S. and Clouvas، نويسنده , , A. and Silva، نويسنده , , J.، نويسنده ,
Abstract :
Experimental and simulated photon flux energy distributions in different locations of a MAYAK PA work place are compared. The experimental photon fluxes are deduced by in situ gamma spectrometry measurements with a portable Germanium detector. The method used for the conversion of the in situ gamma ray spectra to photon flux energy distribution is the spectral stripping method. This method requires the simulation of the portable Germanium detector, which has been performed with the MCNP code of Los Alamos and the GEANT code of CERN. The calculated (simulated) photon flux energy distributions were performed with the MCNP code. The results obtained from the comparison of the experimental and calculated photon flux energy distributions are presented and discussed.
Keywords :
Radiation Protection , gamma spectroscopy , Monte Carlo simulations , MAYAK PA