Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
Crossref DOI link: https://doi.org/10.1007/s10512-018-0446-x
Published Online: 2018-11-24
Published Print: 2018-12
Update policy: https://doi.org/10.1007/springer_crossmark_policy
Dolganov, K. S.
Kiselev, A. E.
Ryzhov, N. I.
Tomashchik, D. Yu.
Filippov, F.
Chalyi, R. V.
Yudina, T. A.
Shevchenko, S. A.
Yashnikov, D. A.
Kozlova, N. A.
Text and Data Mining valid from 2018-11-24
Article History
Received: 10 May 2018
First Online: 24 November 2018