Rapid vitrification of simulated HLLW by ultra-high power laser
Author:
Funder
The Wuhan Municipal Science and Technology Major Project
Publisher
Springer Science and Business Media LLC
Link
https://link.springer.com/content/pdf/10.1007/s10967-024-09467-w.pdf
Reference30 articles.
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2. Wei M, Qiao D, Chen J et al (2023) Study on the benefit of HLLW partitioning on the high-level waste glasses from the viewpoint of waste management. Prog Nucl Energy 160:104672. https://doi.org/10.1016/j.pnucene.2023.104672
3. Lee CW, Shin SG, Kye YU et al (2020) Evaluation of thermal stability in deep geological repository and nuclear criticality safety of spent nuclear fuel vitrified in iron phosphate glass. Ann Nucl Energy 136:107055. https://doi.org/10.1016/j.anucene.2019.107055
4. Järvine AK, Murchison AG, Keech PG et al (2020) A probabilistic model for estimating the life expectancy of used nuclear fuel containers in a canadian geological repository: effects of latent defects and repository temperature. Nucl Technol 206(7):1036–1058. https://doi.org/10.1080/00295450.2019.1700730
5. Gupta VB, Pal TK, Bajpai RK (2020) Development of artificial neural network-based model for prediction of temperature field in host rock of a geological disposal facility for radioactive waste. Curr Sci India 118(3):439. https://doi.org/10.18520/cs/v118/i3/439-443
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