id="par0005">Actinides input to the dose in RBMK-1500 reactor graphite was estimated.
•
id="par0010">SCALE 6.1 and MCNPX models were used to calculate actinides specific activities.
•
id="par0015">ORIGEN-ARP was used for gamma power, neutron source and effective dose calculation.
•
id="par0020">Concentrations of Pu, Am and Cm isotopes in the RBMK graphite sample were measured.
•
id="par0025">244Cm was found to be a critical contributor to effective dose of the personnel.
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