Characterisation of RBMK-1500 graphite: A method to identify the neutron activation and surface contamination terms

V. Remeikis,R. Plukienė,A. Plukis, V. Barkauskas,A. Gudelis,R. Druteikienė,R. Gvozdaitė,L. Juodis,G. Duškesas,E. Lagzdina,D. Germanas,D. Ridikas, S. Krutovcov

Nuclear Engineering and Design（2020）

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摘要

•Spent graphite characterization using modelling and nuclear spectrometry.•Method for neutron activation and surface contamination terms identification.•Ignalina NPP Unit I graphite model validation by nuclear spectrometry measurement.•SCALE 6.2 code use for neutron activation calculation of RBMK reactor graphite.•Important results for decommissioning process of the RBMK type reactors.

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关键词

Irradiated graphite,RBMK-1500 reactor,Nuclear spectrometry,SCALE 6.2 modeling

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