Galina A. Vityuk

Dissertation topic

Investigation of parameters of fuel elements in irradiating experiments in a pulsed graphite reactor

Domestic scientific consultant

Mazhyn K. Skakov, Doctor of Physical and Mathematical Sciences, Professor. Chief Researcher of the Department of Budget Programs and Personnel Training of the National Nuclear Center of the Republic of Kazakhstan, Kurchatov, Republic of Kazakhstan.

Hirsch index – 7 according to the Scopus database. Scopus Author ID: https://www.scopus.com/authid/detail.uri?authorId=6506859122.

Foreign scientific consultant

Alexander V. Gradoboev, Doctor of Technical Sciences, Professor of the Department of Natural Science Education, Yurga Technological Institute, Tomsk Polytechnic University, Tomsk, Russian Federation.

Hirsch index – 6 according to the Scopus database. Scopus Author ID: https://www.scopus.com/authid/detail.uri?authorId=6506370250.

Main scientific results

1. The issue of detailed forecasting and calculation justification of the thermophysical parameters of tests of model fuel elements in the IGR reactor was solved.

2. A method for determining the amount of impurity gases released from the fuel during irradiation has been developed and tested in a series of reactor experiments.

3. Approaches ensuring a given volume distribution of energy release in the tested fuel elements are formulated, justified and experimentally tested.

Direct result

The use of the developed methods and approaches allows improving the quality of specified parameter implementation and accuracy of predicting the results of fuel tests in the conditions of a research reactor. The proposed approaches have been successfully applied in conducting a reactor experiment to study parameters of processes occurring at the initial stage of a severe accident of a fast neutron reactor with a heterogeneous core at the termination of the flow of sodium coolant and can be used in the preparation and implementation of a wide range of experimental programs related to testing of reactor fuel in research reactors.

Scientific works

1. Galina Vityuk, Alexander Vurim, Mazhyn Skakov, Alexander Pakhnits. Methods and results of determining the impurity gas amount in ceramic fuel. Annals of Nuclear Energy, Vol. 150, 2021, 107843. https://doi.org/10.1016/j.anucene.2020.107843. (Indexed by Scopus and ISI Web of Science, quartile Q2 (NUCLEAR SCIENCE & TECHNOLOGY). SJR 2019: 0.918, CiteScore 2019: 2.9, percentile Scopus 69% (Nuclear Energy and Engineering), Impact Factor 1.378.

2. Vityuk V.A., Vityuk G.A., Skakov M.K., Zhagiparova L.K. Design-basis justification for implementing targeted energy release in test objects of the IGR reactor. Eurasian Physical Technical Journal, Vol.17 No.2 (34), 2020, –pp. 87-95. DOI:10.31489/2020No2/87-95. https://up.ksu.kz/phtj/2020_17_2_34/13.pdf. (Indexed by Scopus. CiteScore 2019: 0.2, percentile Scopus 16% (General Energy).

3. Vityuk G.A., Vityuk V.A., Vurim A.D., Kotov V.M., Serre F., Payot F., Suteau C., Trotignon L. Development of a model fuel assembly for investigating an emergency with instant flow blockage coolant in a fast neutron reactor. Bulletin of the National Nuclear Center of the Republic of Kazakhstan, Vol. 3, 2018 –pp.93-98. https://static.nnc.kz/articles/2018_3_17.pdf. Recommended by CCSES RK. Impact factor for KazCB 0.098 (2018)

4. Skakov M.K., Irkimbekov R.A., Vurim A.D., Vityuk G.A., Murzagalieva A.A. Application of the model of spatial kinetics in experiments on the IGR. KazNRTU Bulletin, Vol. 6, 2018 –pp. 351-357. https://vestnik.satbayev.university/index.php/journal/issue/view/43/42. Recommended by CCSES RK. Impact factor for KazCB 0.038 (2018)

5. Skakov M.K., Vityuk G.A., Vityuk V.A., Kotov V.M., Zhanbolatov O.M. Realization of the profile of energy release in a heterogeneous fuel element during tests in a pulsed graphite reactor. KazNRTU Bulletin, Vol. 6, 2018 –pp. 357-364. https://vestnik.satbayev.university/index.php/journal/issue/view/43/42. Recommended by CCSES RK. Impact factor for KazCB 0.038 (2018)

6. Berezovskaya I.E., Toleubekov K.O., Vityuk G.A. Modeling of thermophysical processes in a fast neutron nuclear reactor. Bulletin of the Kazakh National University named after Al-Farabi. Physical series, No. 3 (70), 2019 –pp. 64-72. https://doi.org/10.26577/RCPh-2019-i3-8. Recommended by CCSES RK. Impact factor for KazCB 0.024 (2018)

7. Vityuk V.A., Vurim A.D., Vityuk G.A. Practical methods for determining the energy parameters of reactor tests in the mode of pulsed power variation. Bulletin of the National Nuclear Center of the Republic of Kazakhstan, Vol. 2 (82), 2020, –pp. 80-86. https://static.nnc.kz/articles/2020_2_12.pdf. Recommended by CCSES RK. Impact factor for KazCB 0.098 (2018)

8. Vityuk V.A., Vityuk G.A. Approaches to determining the parameters of heat removal from model fuel assemblies during tests in the IGR reactor. Vestnik of D. Serikbaev EKTU, Vol. 4 (90), December, 2020. –pp. 86-92. /files/vestnik/Vestnik_4-2020.pdf. Recommended by CCSES RK. Impact factor for KazCB 0.023 (2018).

The Hirsch index

Hirsch index – 1 according to the Scopus database.

Scopus Author ID: https://www.scopus.com/authid/detail.uri?authorId=56180224400.

Funded research projects

Projects with grant funding of the Science Committee of the MES RK:

• AP05133086-OT-19. “Properties and characteristics of the melt of materials in the core of a nuclear reactor, obtained at the IGR research reactor”. (2018-2020).
• AP08856242-OT-20. “Optimization of the nuclear fuel campaign for the IVG.1M reactor”. (2020-2022).
• AP09058353. “Development of tools for modeling the dynamics of the neutron field of a pulsed research nuclear reactor". (2021-2023).

Projects of program-targeted financing of the MES RK:

• 61415 / PCF-ME RK-OT-20 “Investigations of the processes occurring during a severe accident in the core of a fast neutron reactor”. (2018-2020).
• BR09158470. “Development of nuclear energy in the Republic of Kazakhstan”. (2021-2023).

Level of foreign language proficiency

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