The objective of WP5 Graphite was to understand the factors determining release of 14C from irradiated graphite (i-graphite) under geological disposal conditions. This was achieved through:
The published reports are:
The last General Assembly Meeting has been held in France (Lyon) in January 2018 as the CAST Final Symposium. Presentations from this work package were:
Overview of main WP5 outcomes, summary and conclusions - Simon Norris (NDA)
Ion irradiation used as surrogate for neutron irradiation to understand nuclear graphite evolution during reactor operation : consequence for long lived radionuclide behaviour - Nelly Toulhoat (IPNL)
14C in TRIGA irradiated graphite and its release under alkaline conditions - Crina Bucur (RATEN ICN)
Oldbury graphite for RWM - Steve Swanton (Wood)
New concept and instruments for 14C measurements in i-graphite - Gérard Laurent (Integrated Nuclear Engineering Solutions)
Posters that were presented and are relevant for this workpackage were:
C-14 enrichment of surface deposits in Oldbury reactor core graphite
The measurement of impurity of RBMK-1500 graphite
14C leaching and speciation studies on irradiated graphite from Vandellós I NPP
A study of graphite from RBMK-type reactors
Characterization of 14C in neutron irradiated RBMK-1500 graphite
Contact: Simon Norris