Preparation and Characterization of Borosilicate Glass Waste Form for Immobilization of HLW from WWER Spent Nuclear Fuel Reprocessing

Stefanovsky, S.V.; Skvortsov, M.V.; Stefanovsky, O.I.; Nikonov, B.S.; Presniakov, I.A.; Glazkova, I.S.; Ptashkin, A.G.

Авторы: Stefanovsky S.V., Skvortsov M.V., Stefanovsky O.I., Nikonov B.S., Presniakov I.A., Glazkova I.S., Ptashkin A.G.
Журнал: MRS Advances
Том: 2
Номер: 11
Год издания: 2017
Первая страница: 583
Последняя страница: 589
DOI: 10.1557/adv.2016.622
Аннотация: Borosilicate glassy materials for immobilization of HLW from Russian WWER ( PWR) spent nuclear fuel reprocessing were designed, synthesized in a resistive furnace, and characterized by XRD, SEM/EDS, and FTIR spectroscopy. Chemical durability was determined by PCT-A procedure and compared to EPA glass and reference data. The glasses with 20 and 25 wt.% waste loading were found to be X-ray amorphous, homogeneous and chemically durable. Glass network formally had a relatively low degree of connectedness that was increased due to embedding of different structural groups thus improving chemical durability. Boron is present primarily in trigonal oxygen coordination. The glasses with 40-45 wt.% waste loading contained minor britholite phase concentrating rare earth elements and as expected trivalent actinides. Glassy product with up to 30 wt.% waste loading was also produced by cold crucible inductive melting at the IPCE RAS lab-scale unit equipped with 56 mm inner diameter copper cold crucible and energized from a 10 kW/5.28 MHz generator. The product was composed of vitreous phase and minor britholite with average composition K0.39Sr1.99Fe0.16Nd5.50Si7.96O26.60.
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Preparation and Characterization of Borosilicate Glass Waste Form for Immobilization of HLW from WWER Spent Nuclear Fuel Reprocessingстатья