1. Grundmann U., Rohde U., Mittag S., Kliem S. DYN3D version 3.2 code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements. Dresden, Forschungszentrum Rossendorf Publ., 2005. 146 p. Available at: https://www.hzdr.de/publications/PublDoc-750.pdf (accessed 10 January 2023).
2. Rohde U., Kliem S., Grundmann U., Baier S., Bilodid Y., Duerigen S., Fridman E., Gommlich A., Grahn A., Holt L., Kozmenkov Ya., Mittag S. The reactor dynamics code DYN3D – models, validation and applications. Progress in Nuclear Energy, 2016, vol. 89, pp. 170–190. https://doi.org/10.1016/j.pnucene.2016.02.013
3. Leppänen J., Pusa M. Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. Proceedings of the International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009). Saratoga Springs, New York, May 3–7, 2009. New York, 2009, pp. 1662–1673. Available at: https://publications.vtt.fi/julkaisut/muut/2009/MC2009.pdf (accessed 10 January 2023).
4. Leppänen J., Pusa M., Viitanen T., Valtavirta V., Kaltiaisenaho T. The Serpent Monte Carlo code: Status, development and applications in 2013. Annals of Nuclear Energy, 2015, vol. 82, pp. 142–150. https://doi.org/10.1016/j.anucene.2014.08.024
5. Piovezan P., Carluccio T., Domingos D. B., Rossi P. R., Mura L. F. On the use of Serpent Monte Carlo code to generate few group diffusion constants. Proceedings of the International Nuclear Atlantic Conference – INAC 2011. Belo Horizonte, MG, Brazil, October 24–28, 2011. Brasilia, 2011.
6. Fridman E., Leppänen J. On the use of the Serpent Monte Carlo code for few-group cross section generation. Annals of Nuclear Energy, 2011, vol. 38, pp.1399–1405. https://doi.org/10.1016/j.anucene.2011.01.032
7. Ovdiienko I., Ieremenko M., Kuchin A., Khalimonchuk V. Development of cross-section library for DYN3D code. Yaderna ta radіatsіina bezpeka = Nuclear and Radiation Safety, 2014, no. 4 (64), pp. 22–25 (in Ukrainian). https://doi.org/10.32918/nrs.2014.4(64).04
8. Herman B. R., Forget B., Smith K., Aviles B. N. Improved diffusion coefficients generated from Monte Carlo codes. Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering – M&C 2013. Sun Valley, Idaho, May 5–9, 2013. New York, 2013, pp. 2947–2961.
9. Hebert A. Applied Reactor Physics. Montreal, Ecole Polytechnique De Montreal Publ., 2009. 424 p.
10. Sánchez-Cervera S., García-Herranz N., Herrero J. J., Cabellos O. Optimization of multidimensional cross-section tables for few-group core calculations. Annals of Nuclear Energy, 2014, vol. 69, pp. 226–237. https://doi.org/10.1016/j.anucene.2014.02.013
11. Smith K. S. Nodal diffusion methods and lattice physics data in LWR analyses: Understanding numerous subtle details. Progress in Nuclear Energy, 2017, vol. 101, pp. 360–369. https://doi.org/10.1016/j.pnucene.2017.06.01
12. Rudziankou I., Babichev L. DYN3D IWQS = 24 library generation using Monte Carlo code Serpent for VVER. Nonlinear Dynamics and Applications. Nonlinear Phenomena in Complex Systems: Proceedings of the 29th International Seminar, Minsk, May 18–21, 2022. Minsk, 2022, vol. 28, pp. 61–65.
13. Babichev L. F., Harokhau Y. Few-group cross section library generation for using Serpent Monte Carlo code and multidimensional fitting. Nonlinear Dynamics and Applications. Nonlinear Phenomena in Complex Systems: Proceedings of the 26th International Seminar, Minsk, May 21–24, 2019. Minsk, 2019, vol. 25, pp. 70–73.
14. Babichev L. F., Harochau Ja. S. Generation of few-group cross section library for reflector of VVER reactor with MCU-PD Monte Carlo code. Nonlinear Dynamics and Applications. Nonlinear Phenomena in Complex Systems: Proceedings of the 25th International Seminar, Minsk, May 21–23, 2018. Minsk, 2018, vol. 24, pp. 7–11.
15. Usheva K. I., Kuten S. A., Khruschinsky A. A., Babichev L. F. Generation of XS library for the reflector of VVER reactor core using Monte Carlo code Serpent. Journal of Physics: Conference Series, 2017, vol. 781, art. ID 012029. https://doi.org/10.1088/1742-6596/781/1/012029
16. Dwiddar M. S., Badawi A. A., Abou-Gabal H. H., El-Osery I. A. From VVER-1000 to VVER-1200: investigation of the effect of the changes in core. PHYTRA 3 – The Third International Conference on Physics and Technology of Reactors and Applications. Tetouan, Morocco, May 12–14, 2014. Rabat, Morocco, 2014. 13 p. Available at: https://From_VVER-1000_to_VVER-1200_Investigation_of_the_effect_of_the_Changes_in_Core-libre.pdf (accessed 10 January 2023).
17. Louis H. K. Neutronic analysis of the VVER-1200 under normal operating conditions. Journal of Nuclear and Particle Physics, 2021, vol. 11, no. 3, pp. 53–66.
18. Semchenkov Y., Styrin Yu. Advancing of VVER reactor core. Proceedings of the International Nuclear Forum on Nuclear Energy – challenges and prospects (BULATOM), Varna, Bulgaria, Jun 9–11, 2010. 31 p. Available at: https://inis.iaea.org/collection/NCLCollectionStore/_Public/45/045/45045684.pdf?r=1 (accessed 10 January 2023).
19. Hafez N., Shahbunder H., Amin E., Elfiki S. A., Abdel-Latif A. Study on criticality and reactivity coefficients of VVER-1200 reactor. Progress in Nuclear Energy, 2021, vol. 131, art. ID 103594. https://doi.org/10.1016/j.pnucene.2020.103594
20. Dwiddar M. S., Badawi A. A., Abou-Gabal H. H., El-Osery I. A. Investigation of different scenarios of thorium–uranium fuel distribution in the VVER-1200 first core. Annals of Nuclear Energy, 2015, vol. 85, pp. 605–612. https://doi.org/10.1016/j.anucene.2015.06.015
