Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
Titel:
Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
Auteur:
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.