Author:
Avvakumov A. V.,Kiselev A. E.,Mitenkova E. F.,Strizhov V. F.,Tarasov V. I.,Tsaun S. V.,Bezlepkin V. V.,Potapov I. A.,Frolov A. S.
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering
Reference6 articles.
1. V. I. Tarasov, BONUS 1.2 Package. Radionuclide Production in Thermal Reactors. User Guide, IBRAE RAN, NSI-SARR-137-2002.
2. M. S. Veshchunov, V. D. Ozrin, V. E. Shestak, et al., “Development of the mechanistic code MFPR for modeling fission-product release form irradiated UO2 fuel,” Nucl. Eng. Des., 236, 179–200 (2006).
3. M. S. Veshchunov, R. Dubourg, V. D. Ozrin, et al., “Mechanistic modeling of uranium fuel evolution and fission product migration during irradiation and heating: the MFPR code,” J. Nucl. Mater., 362, 327–335 (2007).
4. A. V. Berdyshev, M. S. Veshchunov,V. D. Ozrin, et al., Mechanistic Code RELIZ, Autonomous Ver. 1.02. User Guide, IBRAE RAN, NSI-SARR-116-2001.
5. L. Bolshov and V. Strizhov, “SOCRAT – the system of codes for realistic analysis of severe accidents,” in: Proc. ICAPP’06, Reno, USA, June 4–8, 2006, Paper 6439.
Cited by
8 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献