TAG 3.1 Fuel and engineered barrier system
ABCRad – Alternative Buffer/Backfill Characterisation + Radionuclide Interactions, HU
Research reports:
Vettese, G. 2023. ABCRAD Deliverable 1: Desktop study and basic characterisation of alternative buffer materials. University of Helsinki. 11 p.
Theses:
Silenius, K. 2024. Chemistry and sorption capacity of two alternative bentonites for use in the Finnish spent nuclear fuel repository. Master’s Thesis, University of Helsinki. 63 p. https://helda.helsinki.fi/items/3db7eb94-bbc6-4bc4-aece-0f4f47db5990
DEHYDSU – Defects, hydrogen and susceptibility of Cu-OFP to stress corrosion cracking in sulphide containing environment, VTT
Research reports:
Goel, S., Ikäläinen, T., Saario, T. 2023. Surface microcracks in Cu-OFP exposed to air or water with sulphides. VTT Research Report, VTT-R-00761-23. 25 p.
MOCRYCO – Model based on crystal plasticity for copper, VTT
SAGE – Sensitivity analysis guided disposal barrier experiments, VTT, JyU, GTK
Theses:
Harjupatana, T. 2023. Monitoring water transport and deformation in swelling materials using X-ray imaging and tomography. Academic dissertation, Faculty of Mathematics and Science of the University of Jyväskylä. 119 p.
Database:
A collection of THMCG data on bentonite and bentonite-based mixtures. www.bentonitedata.com