Abstract
− Using first principles calculations we investigated the thermomechanical stability of spent nuclear fuels (SNF), especially how mechanical properties of UO2, such as, bulk, shear and Young’s moduli and Poisson’s ratio vary through alpha-decay of U into Th with generation of He gas. Our results indicate that substitution of U by Th through alpha decay (U1-xThxO2) does not significantly affect the stability of the grain in a fuel matrix. In addition, we studied the transport properties of He in and boUndaries of the U1-xThxO2 grain. Helium preferentially resides at the grain boUndaries through diffusion. Our study can contribute to substantial reduction of environmentally risk and enhancement of our sustainability by safe control of radioactive materials.
Original language | English |
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Pages (from-to) | 368-371 |
Number of pages | 4 |
Journal | Korean Chemical Engineering Research |
Volume | 57 |
Issue number | 3 |
DOIs | |
Publication status | Published - 2019 |
Bibliographical note
Funding Information:The Nuclear R&D Program funded by the Ministry of Science and ICT (2016M2B2B1945254) supported this research. This work was also supported by the Global Frontier Pro-gram through the Global Frontier Hybrid Interface Materials (GFHIM) (2013M3A6B1078882) funded by the Mistry of Science and ICT.
Funding Information:
The Nuclear R&D Program fUnded by the Ministry of Science and ICT (2016M2B2B1945254) supported this research. This work was also supported by the Global Frontier Pro-gram through the Global Frontier Hybrid Interface Materials (GFHIM) (2013M3A6B1078882) fUnded by the Mistry of Science and ICT.
Publisher Copyright:
© 2019 Korean Institute of Chemical Engineers. All rights reserved.
All Science Journal Classification (ASJC) codes
- Chemical Engineering(all)