TY - JOUR
T1 - Characterisation of RBMK-1500 graphite
T2 - A method to identify the neutron activation and surface contamination terms
AU - Remeikis, V.
AU - Plukienė, R.
AU - Plukis, A.
AU - Barkauskas, V.
AU - Gudelis, A.
AU - Druteikienė, R.
AU - Gvozdaitė, R.
AU - Juodis, L.
AU - Duškesas, G.
AU - Lagzdina, E.
AU - Germanas, D.
AU - Ridikas, D.
AU - Krutovcov, S.
PY - 2020
Y1 - 2020
N2 - In this study, we provide the results of radiological characterization of the RBMK-1500 graphite using modeling and nuclear spectrometry; we also introduce a method to identify neutron activation and surface contamination terms for the spent graphite waste. The simplified model of the reactor core created by programme package SCALE 6.2 for 4 × 4 fragment of the core was used for simulation of neutron activation of graphite impurities in the RBMK-1500 reactor. Calculations were supplemented by the non-destructive measurements of gamma-ray emitting nuclides and destructive analysis of selected samples of the graphite stack of Ignalina NPP Unit 1 reactor. Our analysis demonstrates that the partial contribution of different contamination sources can be identified by combining modeling and measurements. The findings on radionuclides such as 14C, 36Cl, 60Co, 134Cs, 137Cs, 154Eu as well as actinides in Ignalina NPP Unit 1 graphite having a significant impact on graphite activity and radiological characterization are discussed. The proposed method is also applicable for identification of contamination source in the other activated components of the reactor core.
AB - In this study, we provide the results of radiological characterization of the RBMK-1500 graphite using modeling and nuclear spectrometry; we also introduce a method to identify neutron activation and surface contamination terms for the spent graphite waste. The simplified model of the reactor core created by programme package SCALE 6.2 for 4 × 4 fragment of the core was used for simulation of neutron activation of graphite impurities in the RBMK-1500 reactor. Calculations were supplemented by the non-destructive measurements of gamma-ray emitting nuclides and destructive analysis of selected samples of the graphite stack of Ignalina NPP Unit 1 reactor. Our analysis demonstrates that the partial contribution of different contamination sources can be identified by combining modeling and measurements. The findings on radionuclides such as 14C, 36Cl, 60Co, 134Cs, 137Cs, 154Eu as well as actinides in Ignalina NPP Unit 1 graphite having a significant impact on graphite activity and radiological characterization are discussed. The proposed method is also applicable for identification of contamination source in the other activated components of the reactor core.
KW - Irradiated graphite
KW - Nuclear spectrometry
KW - RBMK-1500 reactor
KW - SCALE 6.2 modeling
U2 - 10.1016/j.nucengdes.2019.110501
DO - 10.1016/j.nucengdes.2019.110501
M3 - Article
AN - SCOPUS:85077926608
SN - 0029-5493
VL - 361
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 110501
ER -