E
E. V. Marova
Publications - 7
Citations - 73
E. V. Marova is an academic researcher. The author has contributed to research in topics: Nuclear reactor core & MOX fuel. The author has an hindex of 4, co-authored 7 publications receiving 70 citations.
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Journal ArticleDOI
Neutronic features of the GT-MHR reactor
N. G. Kodochigov,Yu.P. Sukharev,E. V. Marova,N. Ponomarev-Stepnoy,E. S. Glushkov,P. A. Fomichenko +5 more
TL;DR: In this paper, the authors describe the analysis of the basic features of the GT-MHR reactor core fueled by plutonium, and the temperature coefficient of reactivity depends both on the temperature and burnup level.
Journal ArticleDOI
Efficiency Assessment of Nuclear Energy Development Scenarios for Russia Using Multi-Criteria Analysis
P. N. Alekseev,V. Yu. Blandinskii,A. L. Balanin,A. V. Grol,V. A. Nevinitsa,P. S. Teplov,P. A. Fomichenko,A. V. Gulevich,V. M. Dekusar,A.F. Egorov,V. V. Korobeinikov,A. L. Moseev,E. V. Marova,A. M. Maslov,M. R. Farakshin,S. F. Shepelev,A. V. Shirokov +16 more
TL;DR: The results of a multi-criteria systems analysis of alternative scenarios for the development of nuclear energy in Russia performed using international assessment tools are reported.
Journal ArticleDOI
Computational and experimental investigations of the neutron-physical characteristics of the GT-MHR core
N. G. Kodochigov,Yu. P. Sukharev,E. V. Marova,V. F. Boyarinov,V. I. Bryzgalov,E. S. Glushkov,E. A. Gomin,M. I. Gurevich,V. D. Davidenko,G. V. Kompaniets,A. M. Krutov,V. A. Nevinitsa,P. A. Fomichenko,V. F. Tsibul’skii,M. S. Yudkevich,E. F. Mitenkova,N. V. Novikov +16 more
TL;DR: In this paper, the main results of computational and experimental investigations of the neutron-physical characteristics of the GT-MHR high-temperature gas-cooled reactor are presented: analysis of the possible reasons for the uncertainties in the calculations of the NPP of a core with plutonium fuel using different computer programs.
Journal ArticleDOI
Possibility of operating gt-mhr with different fuels
TL;DR: In this article, the results of a computational investigation of the neutron-physical characteristics and parameters of GT-MHR for different fuels are presented: weapons grade plutonium, reactor plutonium, low-enrichment uranium, mixed fuel based on uranium and weapons-grade plutonium, fuel with added americium and curium.
Journal ArticleDOI
Profiling of energy deposition fields in a modular HTHR with annular core: Computational/experimental studies at the ASTRA critical facility
V. F. Boyarinov,V. P. Garin,E. S. Glushkov,A. A. Zimin,G. V. Kompaniets,V. A. Nevinitsa,D. N. Polyakov,A. S. Ponomarev,N. N. Ponomarev-Stepnoi,O. N. Smirnov,P. A. Fomichenko,E. I. Chunyaev,E. V. Marova,Yu. P. Sukharev +13 more
TL;DR: In this paper, the spatial distribution of the 235U fission reaction rate in a critical assembly with an annular core and poison profiling elements inserted into the inner graphite reflector was analyzed.