title: Assessment and benchmarking of the impact to gamma dose rate employing different photon-to-dose conversion factors using MCNPX code at the decommissioning stage of Ignalina Nuclear Power Plant.
abstract: A comparative study was performed to reveal the impact of several photon-to-dose conversion factors for gamma dose rate calculations when applied to heterogeneous environment in the case of decommission stage of the Ignalina Nuclear Power Plant. The following set of conversion factors were investigated by employing the Monte Carlo N-particle transport (MCNPX) code derived from the recommendations given in ICRP-21, ICRP-74 and ANSI/ANS-6.1.1 standards (1977 and 1991), based on the experiments performed for gamma radiation dose rate measurements inside the deplanting Emergency Core Cooling System tank. MCNPX precise simulation and the benchmark between the conversion coefficients highlighted the impact to the results for the selected case of this investigation. The results revealed that the data from the ANSI/ANS-6.1.1 1991 publication are reliable for various dose and shielding calculations in the case of decontamination of radioactive equipment and similar applications since it showed a statistically satisfied agreement between the simulation results and experimental data. These tendencies suggest that the radiological protection system currently adopted in NPP during the decommissioning stage can be characterised using ANSI/ANS-6.1.1 1991 standards with respect to gamma dosimetry.
authors.affiliation: Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, Kaunas LT-44403, Lithuania gediminas@mail.lei.lt.
authors.forename: Gediminas
authors.initials: G
authors.lastname: Stankunas
authors.affiliation: Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, Kaunas LT-44403, Lithuania.
authors.forename: Raimondas
authors.initials: R
authors.lastname: Pabarcius
authors.affiliation: Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, Kaunas LT-44403, Lithuania.
authors.forename: Aurimas
authors.initials: A
authors.lastname: Tonkunas
mesh_terms: D019985:Benchmarking; D001822:Body Burden; D003198:Computer Simulation; D003666:Decontamination / Q000295:instrumentation*; D005720:Gamma Rays; D006801:Humans; D009010:Monte Carlo Method; D055848:Nuclear Power Plants; D019047:Phantoms, Imaging; D017785:Photons; D011829:Radiation Dosage; D011834:Radiation Monitoring; D011835:Radiation Protection; D011874:Radiometry; D014915:Whole-Body Counting / Q000379:methods*