Ternovyh M.Y.

Ternovyh Mihail Y.

Leading Engineer

Department of Experimental and Theoretical Physics of Nuclear Reactors

Senior Lecturer

Department of Experimental and Theoretical Physics of Nuclear Reactors
Works at MEPhI since 1990
Work Experience: 38 years

Education

1985 — National Research Nuclear University MEPhI

Courses

1. Academic Practice (Introduction)
2. Course project (design and selection of equipment for NPPs, safety and efficiency of NPPs)
3. Industrial workshop (research, physics of nuclear power plants)
4. Practical Training (Research Work)
5. Radiative Transfer Theory
6. Software and Methods for Neuron-physics Calculations
7. Transfer in Nonmultiplying Environments Theory

Publication activity

2
h-index (Web of Science)
4
h-index (Scopus)
4
h-index (РИНЦ)

Showing publications for last 3 years

  1. Article
    Web of Science & Scopus
    Evaluation of technological uncertainties using the sensitivity to nuclear data // Atomic Energy, 2024 Q3 doi
  2. Article
    Web of Science & Scopus
    Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel // Annals of Nuclear Energy, 2024 Vol. 197, Q2 doi
  3. Article
    Web of Science & Scopus
    Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison // Nuclear Energy and Technology, 2023 Vol. 9, No. 3 pp. 157-162 doi
  4. Article
    Web of Science & Scopus
    NUCLEAR DATA UNCERTAINTY ON GENERATION IV FAST REACTORS CRITICALITY CALCULATIONS ANALYSIS COMPARISON СРАВНИТЕЛЬНЫИ АНАЛИЗ НЕОПРЕДЕЛЕННОСТЕИ РАСЧЕТА КРИТИЧНОСТИ БЫСТРЫХ РЕАКТОРОВ ПОКОЛЕНИЯ IV, ВНОСИМЫХ ЯДЕРНЫМИ ДАННЫМИ // Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika, 2023 Vol. 2023, No. 1, Q4 pp. 162-174 doi
  5. Article
    Web of Science & Scopus
    Nuclear data uncertainty influence on the breeding ratio in sodium-cooled fast reactor systems // Annals of Nuclear Energy, 2023 Vol. 188, Q2 doi
  6. Article
    Web of Science & Scopus
    Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP // Physics of Atomic Nuclei, 2022 Vol. 85, Q4 pp. S90-S102 doi
  7. Article
    Web of Science & Scopus
    Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis // Journal of Nuclear Science and Technology, 2022 Q2 doi
  8. Article
    Web of Science & Scopus
    Independent testing of new generation codes of the Proryv project // Nuclear Engineering and Design, 2021 Vol. 384, Q1 doi

Showing conferences for last 3 years

  1. Сентябрь 2022 International Conference for young scientists, specialists and post-graduates on Nuclear Reactor Physics (ICNRP Volga-2022) Report: Nuclear data uncertainty impact assessment on GEN IV fast reactors calculations

Повышение квалификации

April 12, 2021 — April 16, 2021 SCALE TRAINING COURSE SENSITIVITY AND UNCERTAINTY ANALYSIS FOR CRITICALITY SAFETY ASSESSMENT AND VALIDATION (48 hours) NEA DATA BANK, BOULOGNE-BILLANCOURT, FRANCE

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