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Hire Dr. Maxat B.

Kazakhstan

USD 50 /hr

I am a PhD in Technical Physics with research experience in reactor safety and nuclear engineering.

Profile Summary

My work focuses on safety assessment, engineering analysis, scientific research, and technical documentation. I provide support for researchers, graduate students, and academic institutions in the preparation, review, and improvement of scientific documents.

Subject Matter Expertise

• ☆ Engineering Physics
• ☆ Nuclear Physics
• ☆ Nuclear Power

Services

• Writing
• Research
• Consulting

Writing Technical Writing

Research Scientific and Technical Research

Consulting Scientific and Technical Consulting

Work Experience

Head of the Laboratory

Institute of Atomic Energy NNC RK

November 2009 - Present

Education

PhD in Technical Physics

Shakarim University

September 2020 - August 2023

Certifications

• Instructor training course Reactor Engineering

  JAEA, Japan

  August 2018 - November 2018

• Training course for specialists in the field of nuclear energy

  JAEA, Japan

  November 2012 - November 2012

Publications

JOURNAL ARTICLE

Maxat Bekmuldin, Kuanyshbek Toleubekov, Ivan Kukushkin, Arman Miniyazov, Asan Akayev, Nurzhan Mukhamedov, Alexander Gulkin (2026). Study of the interaction between a sacrificial material based on ceramic Al2O3 with metallic Sb and corium under ex-vessel melt retention conditions. Part 1 . Annals of Nuclear Energy.

Maxat Bekmuldin, Kuanyshbek Toleubekov, Nurzhan Mukhamedov, Artur Surayev, Galina Vityuk, Peter Ivanov (2026). Decommissioning of a Nuclear Facility With Sodium‐Cooled Fast Reactor as a Final Stage of Its Life Cycle: Overview of Current Projects . Science and Technology of Nuclear Installations.

Maxat Bekmuldin, Nurzhan Mukhamedov, Kuanyshbek Toleubekov, Galina Vityuk, Sergey Dolzhikov (2025). Decommissioning of the BN-350 Fast Neutron Reactor: History Review and Current Status . Energies.

(2024). THERMAL TECHNOLOGICAL CONDITION OF IVG.1M RESEARCH REACTOR CORE UNDER VARIOUS OPERATING MODES . Eurasian Physical Technical Journal.

Maxat Bekmuldin, Mazhyn Skakov, Viktor Baklanov, Ivan Kukushkin, Kuanyshbek Toleubekov, Assan Akaev, Madi Azbergenov, Yerkhat Dauletkhanov, Adil Toktaushev (2024). Investigation of the interaction between corium and metal-coolers at the VCG-135 test bench in the conditions of a severe accident . Nuclear Engineering and Design.

Maxat Bekmuldin, Kuanyshbek Toleubekov, Mazhyn Skakov, Viktor Baklanov, Assan Akaev (2024). Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident . International Journal of Advanced Nuclear Reactor Design and Technology.

Maxat Bekmuldin, M.K. Skakov, National Nuclear Center of the Republic of Kazakhstan, Kurchatov, Kazakhstan (2024). ANALYSIS OF METHODS FOR SIMULATING THE DECAY HEAT IN CORIUM WHEN MODELING A SEVERE ACCIDENTS AT NUCLEAR POWER PLANT . Eurasian Physical Technical Journal.

M.K. Skakov, V.V. Baklanov, I.M. Kukushkin, M.K. Bekmuldin, A.S. Akaev, M.N. Azbergenov, A.V. Gradoboev (2024). The main structural-phase states of interaction between model corium of a nuclear reactor and a sacrificial material based on Al2O3 and a lead layer . International Journal of Advanced Nuclear Reactor Design and Technology.

M. K. Bekmuldin, М. K. Skakov, V. V. Baklanov, А. V. Gradoboev, A. S. Akayev, K. O. Toleubekov (2024). Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench . Nuclear Technology.

Bekmuldin, Maxat, Skakov, Mazhyn, Baklanov, Viktor, Kukushkin, Ivan, Toleubekov, Kuanyshbek, Akaev, Assan, Azbergenov, Madi, Dauletkhanov, Yerkhat, Toktaushev, Adil (2024). Investigation of the interaction between corium and metal-coolers at the VCG-135 test bench in the conditions of a severe accident . Nuclear Engineering and Design.

Bekmuldin, Maxat, Skakov, Mazhyn, Baklanov, Viktor, Kukushkin, Ivan, Akaev, Assan, Gradoboev, Alexander, Stepanova, Olga (2024). Results of experimental simulation of interaction between corium of a nuclear reactor and sacrificial material (Al2O3) with a lead layer . AIMS Materials Science.

Maxat Bekmuldin, Mazhyn Skakov, Viktor Baklanov, Gulnur Nurpaissova, Kuanyshbek Toleubekov, Assan Akayev (2024). EFFECIENCY OF SIMULATING DECAY HEATIN THE CORIUM OF A NUCLEAR REACTOR BY THE OHMIC HEATING METHOD . Recent Contributions to Physics.

Bekmuldin, M. K., Skakov, m. k., Baklanov, V. V., Gradoboev, A. V., Akayev, A. S., Toleubekov, K. O. (2024). Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench . Nuclear Technology.

Maxat Bekmuldin, Andrey Turkach, Alikhan Yediluly, Assan Akaev (2023). A system for plasma density variation based on a gas-dynamic source of a molecular beam . Fusion Engineering and Design.

M. K. Skakov, V. V. Baklanov, K. O. Toleubekov, A. S. Akaev, M. K. Bekmuldin, A. V. Gradoboev(2023). MODELING OF THE CORIUM AND METALS – COOLERS INTERACTION IN A CORE CATCHER OF A LIGHT WATER REACTOR . NNC RK Bulletin. (2). Microsoft.AspNetCore.Mvc.Localization.LocalizedHtmlString 49--57. Republican State Enterprise {\&}quot$\mathsemicolon$National Nuclear Center of the Republic of Kazakhstan{\&}quot$\mathsemicolon$

Maxat Bekmuldin, Mazhyn Skakov, Viktor Baklanov, Assan Akaev, Ivan Kukushkin, Kuanyshbek Toleubekov, Alexandr Gradoboev, Olga Stepanova (2023). On the Possibility of Forming a Corium Pool by Induction Heating in a Melt Trap of the Lava-B Facility . Applied Sciences.

Bekmuldin, Maxat, Turkach, Andrey, Yediluly, Alikhan, Akaev, Assan (2023). A system for plasma density variation based on a gas-dynamic source of a molecular beam . Fusion Engineering and Design.

Bekmuldin, Maxat, Skakov, Mazhyn, Baklanov, Viktor, Akaev, Assan, Kukushkin, Ivan, Toleubekov, Kuanyshbek, Gradoboev, Alexandr, Stepanova, Olga (2023). On the Possibility of Forming a Corium Pool by Induction Heating in a Melt Trap of the Lava-B Facility . Applied Sciences.

Toleubekov, K. O., Baklanov, V. V., Akayev, A. S., Bekmuldin, M. K. (2022). MODELING THE PROCESS OF DECAY HEAT IMITATION IN THE CORIUM AT THE "LAVA-B" FACILITY . Recent Contributions to Physics.

Skakov, M.K., Toleubekov, K.O., Baklanov, V.V., Gradoboev, A.V., Akayev, A.S., Bekmuldin, M.K.(2022). THE METHOD OF CORIUM COOLING IN A CORE CATCHER OF A LIGHT-WATER NUCLEAR REACTOR . Eurasian Physical Technical Journal. 19. (3). Microsoft.AspNetCore.Mvc.Localization.LocalizedHtmlString 69 – 77.

(2021). ПОВЫШЕНИЕ ЭФФЕКТИВНОСТИ ЛОКАЛИЗАЦИИ КОРИУМА В ПОДРЕКТОРНОЙ ЛОВУШКЕ РАСПЛАВА ЛЕГКОВОДНОГО ЯДЕРНОГО РЕАКТОРА .

Bekmuldin, M.K., Skakov, K., Baklanov, V.V., Gradoboyev, A.V., Akaev, A.S.(2021). Heat-Resistant Composite Coating with A Fluidized Bed of the Under-Reactor Melt Trap of A Light-Water Nuclear Reactor . Eurasian Physical Technical Journal. 18. (3). Microsoft.AspNetCore.Mvc.Localization.LocalizedHtmlString 65-70.

ВАКУУМНЫЙ СТЕНД С ГДИ ДЛЯ ОТРАБОТКИ РЕЖИМОВ ПОДПИТКИ И ГАШЕНИЯ ПЛАЗМЫ В КАМЕРЕ ТОКАМАКА КТМ .

ИСПЫТАНИЯ СИСТЕМЫ ИЗМЕНЕНИЯ ПЛОТНОСТИ ПЛАЗМЫ НА ОСНОВЕ ГАЗОДИНАМИЧЕСКОГО ИСТОЧНИКА МОЛЕКУЛЯРНОГО ПУЧКА .

ИССЛЕДОВАНИЕ ПАРАМЕТРОВ ГАЗОВОГО ПОТОКА, ГЕНЕРИРУЕМОГО ГАЗОДИНАМИЧЕСКИМ ИСТОЧНИКОМ .

ИССЛЕДОВАНИЕ ТЕПЛОИЗОЛЯЦИОННЫХ СВОЙСТВ КОРПУСА ПРИЕМА РАСПЛАВА ЭКСПЕРИМЕНТАЛЬНОЙ УСТАНОВКИ ЛАВА-Б .

ПОВЫШЕНИЕ ЭФФЕКТИВНОСТИ СИСТЕМЫ ИНДУКЦИОННОГО НАГРЕВА ДЛЯ ИМИТАЦИИ ОСТАТОЧНОГО ЭНЕРГОВЫДЕЛЕНИЯ В КОРИУМЕ ПРИ ВЗАИМОДЕЙСТВИИ С ЖАРОПРОЧНЫМИ МАТЕРИАЛАМИ .

Maxat Bekmuldin Современные тенденции водородной энергетики и ее перспективы в Казахстане .

MAGAZINE ARTICLE

Maxat Bekmuldin Results of experimental simulation of interaction between corium of a nuclear reactor and sacrificial material (Al2O3) with a lead layer .