Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste.
Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste.
复制标题
高活性放射性废物的容器内玻璃化产品的多废物流的表征和可处置性评估。
DOI:
10.1016/j.jhazmat.2020.123764
复制
发表时间:
2021
影响因子:
13.6
通讯作者:
N. Hyatt
中科院分区:
文献类型:
--
作者:
S. Walling;M. Kauffmann;L. J. Gardner;D. Bailey;M. Stennett;C. Corkhill;N. Hyatt
Materials from GeoMelt® In-Container Vitrification (ICV)™ of simulant UK nuclear wastes were characterised to understand the partitioning of elements, including inactive surrogates for radionuclide species of interest, within the heterogeneous products. Aqueous durability analysis was performed to assess the potential disposability of the resulting wasteforms. The vitrification trial aimed to immobilise a variety of simulant legacy waste streams representative of decommissioning operations in the UK, including plutonium contaminated material, Magnox sludges and ion-exchange materials, which were vitrified upon the addition of glass forming additives. Two trials with different wastes were characterised, with the resultant vitreous wasteforms comprising olivine and pyroxene crystalline minerals within glassy matrices. Plutonium surrogate elements were immobilised within the glassy fraction rather than partitioning into crystalline phases. All vitrified products exhibited comparable or improved durability to existing UK high level waste vitrified nuclear wasteforms over a 28 day period.
影响因子:
3.1
作者:
Hyatt N
通讯作者:
Hyatt N
影响因子:
3.5
作者:
D. Backhouse;C. Corkhill;N. Hyatt;R. Hand
通讯作者:
D. Backhouse;C. Corkhill;N. Hyatt;R. Hand