Mayorov, Lev Vasilievich

L.V. Mayorov graduated with honors from the Physics Department of Moscow State University in 1956 and was sent to work at the Department of Applied Mathematics of the USSR Academy of Sciences, now named after M.V. Keldysh RAS (IPM RAS). Here he began to deal with the problem of thermalization of neutrons - then a little-developed field of neutron physics, and together with V.F. Turchin, he developed the first universal program in the USSR for calculating the scattering cross sections of slow neutrons in a condensed medium. In 1964, these authors presented a report on the effect of chemical bonds on the thermalization of neutrons at the III International Geneva Conference on the Peaceful Use of Atomic Energy.

In 1965 he moved to the Institute of Atomic Energy. I.V. Kurchatova , in which he worked until the end of his life. The main focus of his scientific activity was a theoretical analysis of the results of measurements of the spectra of slow neutrons and phonon spectra of moderators, which were carried out by a group of experimenters under the supervision of a member of the Corr. USSR Academy of Sciences V.I. Bridge .

In 1969, in the IAE. I.V. Kurchatova appeared one of the country's first powerful computer BESM-6 and L.V. Mayorov led the organization of a computer center. In a short time, under his leadership, the necessary software was developed, a mass training and user service system was organized. As a result, modern computer methods have become available to solve theoretical and practical problems that specialists of the IAE named after I.V. Kurchatova .

In 1972, L.V. Mayorov became head of the laboratory for benchmarking nuclear reactors. He is actively involved in the implementation of the Monte Carlo method for solving problems of reactor physics and at the same time offers new improved estimation algorithms for engineering calculations of nuclear reactors.

In 1973, L.V. Mayorov, as part of a team of employees of the IAE and industrial plants of the Ministry of Secondary Engineering, was awarded the USSR State Prize "For research in neutron physics and their use in industry." His work on the estimation of bias in Monte Carlo calculations of large loosely coupled systems - power reactors, nuclear fuel storage facilities - has gained international recognition.

In 1982, L.V. Mayorov, with a team of his students and employees, began work on creating the MCU application package ( Monte Carlo Universal ) at the Kurchatov Institute . The package is intended for modeling the transfer of neutrons, photons, electrons and positrons in neutron multiplying systems of arbitrary geometry by analog and weighted Monte Carlo methods .

Under the leadership and with the direct participation of L. V. Mayorov, the first versions of the package were developed. MCU continues to evolve. Programs of the MCU family are operated in most research, design and technological institutes of the nuclear industry of Russia, in higher educational institutions of the country, transferred to other countries.

L. V. Mayorov collaborated with all reactor units of the Kurchatov Institute . He was an active participant in the Provisional International Team (VMK) for the study of the physics of pressurized water reactors (VVER) . Under his scientific editorship, the final collections of theoretical works of the VMK “Theoretical Studies in the Physics of Uranium-Water Lattices of the WWER Type” were published in Russian and English.

He was buried in Moscow at the Vagankovsky cemetery ^[1] .

1973 - USSR State Prize "For research in the field of neutron physics and their use in industry."

L.V. Mayorov four times became the laureate of the Kurchatov Prize for the best scientific work of the year (1976, 1984, 1992 and 1995).

1. Mayorov L.V. On the effect of flux anisotropy on the temperature of a neutron gas. // ZhVM and MF. T. 2. Issue. 349. 1962.
2. The distribution of neutron flux from the plane source. Proceed. // BNL Therm. Confer / BNL-719 New Youk, v. 4, p. 1375, 1962.
3. Universal program for calculating slow neutron scattering cross sections (URAS). Co-author - Turchin V.F. // Preprint MI Academy of Sciences of the USSR, No. 149. 1963.
4. The effect of chemical bonding on the thermalization of neutrons. Co-author - Turchin V.F. // Proceedings of the III Geneva Conf., New Youk, UN. 1965.
5. Thermalization of neutrons in a graphite-water system. Co-authors - Mostovoi V.I., Safin Yu.A., Trukhanov G. Ya. // Pulsed Neutron Research. Vienna, v. 1, p. 657.1965.
6. Asymptotics of the law of scattering of slow neutrons. // Atomic energy . T. 19. Issue. 67.1965.
7. A new method for reconstructing true spectra. Co-authors - A. Tikhonov et al. // Atomic energy . T. 18. 1965.S. 588.
8. Anisotropy of the neutron spectrum in water near the absorber. Co-authors - Ishmaev et al. // Neutron Thermal. and Reactor Spectra IAEA. Vienna, v. 2, p. 193, 1968 ..
9. Comparative effectiveness of various estimates in the Monte Carlo method. Co-author - Frank-Kamenetsky A.D. // Preprint IAE-1791. 1969.
10. Thermalization of neutrons from a pulsed source. Co-authors - Kazarnovsky M., Yudkevich M. // Sat. Theor and exp. problems nestats. neutron transfer. Atomizdat. 1972.
11. Simulation of collisions in the thermal field. // Paragraph in the book. A. D. Frank-Kamenetsky "Modeling of neutron trajectories in the calculation of reactors using the Monte Carlo method." M., Atomizdat . 1978.P. 46.
12. NEWRAS program for calculating differential cross sections of slow neutrons. Co-author - Lyman G.F. // Sat. Questions of atomic science and technology. Ser. Physics and technology of nuclear reactors. Vol. 8 (21). 1981. S. 32.
13. On the calculation of the probabilities of first collisions in systems with complex geometry. Co-author - Gomin E.A. // Ibid. 1981.P. 62.
14. On the thermalization of neutrons. // Paragraph in the book. I. Kh. Ganeva "Physics and reactor design". M., Energy Publishing House. 1981.P. 235.
15. The software complex MMKFK for the calculation of reactors by the Monte Carlo method, developed by A.D. Frank-Kamenetsky. // Sat Questions of atomic science and technology. Ser. Physics and technology of nuclear reactors. Vol. 8 (21). 1981.P. 10.
16. On the calculation of the constants of diffusion finite difference equations for heterogeneous reactors. // Sat Questions of atomic science and technology. Ser. Physics and technology of nuclear reactors. Vol. 5.1983, p. 3.
17. Estimation of criticality parameters by the Monte Carlo method. Co-author - V. Zolotukhin // Monograph. Energoatomizdat. 1984.
18. Calculation of the neutron flux functionals by the Monte Carlo method in breeding systems with a leak specified by a geometric parameter. // Atomic energy . T. 58. 1985.P. 93.
19. MCU software package for solving the Monte Carlo method of radiation transfer in reactors. Co-authors - Liman G.F., Yudkevich M.S. // Sat. Questions of atomic science and technology. Ser. Physics and technology of nuclear reactors. Vol. 7 1985.P. 27.
20. Calculation of the vapor effect in the polycells of RBMK reactors. Co-authors - V. I. Bryzgalov et al. Calculation of the vapor effect in the polycells of the RBMK reactor with a reduced graphite content in the masonry. Co-authors - Bryzgalov V.I., Gomin E.A. // IAE Reports. No. 36/709786 and 36/711886, 1986.
21. Neutron-physical constants in calculations of thermal neutron reactors. Co-author - Yudkevich M.S. // Monograph. Energoatomizdat, M., 1988
22. MCU application package. MCU-2.0 version. Co-authors - Gomin E.A. et al. // IAE Report. No. 36 / 1-720-89, 1989.
23. Some Aspects of Monte Carlo Method Application to Progress in Nuclear Reactor Analysis. Coauthors - Gomin EA, Yudkevich MS // Progress in Nucl. Sci. Vol. 24, NN 1-3, 1990.
24. The MCU-3 program for Monte Carlo calculation of the neutron-physical characteristics of nuclear reactors. Volume 1-5. Co-authors - Gurevich M.I. et al. // Preprints IAE-5772/5, IAE-5777/5, IAE-5736/5, IAE-5741/5, IAE-5739/5, M. 1994.
25. The MCU-RFFI Monte Carlo Code for Reactor Design Applications. Coauthor- Gomin EA // Proc. of intern. Conf. on Mathem. And Comput., Reac. Phys., And Envir. Analyses, April 30 - May 4, 1995, Portland, Or., USA, Vol. 2 p. 1136.
26. Detection of Hidden Explosives and Drugs. Coauthors - Mostovoy VI, et.al. // Proc. of the Second Explosives Detection Technology Symp. & Aviation Security Technology Conference. November 12-15, 1996, Atlantic City, NY, USA, p. 148.
27. The experimental and Calculational Investigation of Radiation Fields in the SM High Flux Research Reactor. Coauthors - Markina NV et. al. // Proc. of the 9 International Symposium on the Reactor Dosimetry, Sept. 2-6, Prague, Chech Rep., 1996, 12 pp.
28. ALIGR Technique for Reactor Fuel Burn-Up Calculations Using Monte-Carlo Method. Coauthor - Kalugin MA // 1998 ANS Winter Meeting. Washington, DC November 15-19, 1998. Vol. 79, ISSN: 0003-018X, pp. 312-313
29. The MCU Monte-Carlo Code for 3D Depletion Calculation. Coauthor - Gomin EA // Proc. of intern. Conf. on Mathem. And Comput., Reac. Phys., And Envir. Analyses in Nucl. Applications, Sept. 27-30, 1999, Madrid, Spain, Vol. 2 p. 997.
30. Estimates of bias in the calculation of reactors and nuclear fuel storage using the Monte Carlo method. Atomic Energy , 2005, vol. 99, no. 4, p. 243.

• Moscow encyclopedia. Volume 1: Faces of Moscow. Book 6: AZ. Additions. - M.: Moscow Textbooks OJSC, 2014

• Dedicated to the memory of Lev Vasilievich Mayorov (inaccessible link) . Questions of atomic science and technology. Series: Physics of Nuclear Reactors. Issue 1, 2006.
• Lev Vasilievich Mayorov in the virtual museum .