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プロフィール詳細
プロジェクトを作成
★★★★★
☆☆☆☆☆
Dr. Maxat B.に依頼
Kazakhstan

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

プロフィール概要
専門分野
サービス
Writing Technical Writing
Research Scientific and Technical Research
Consulting Scientific and Technical Consulting
職務経験

Head of the Laboratory

Institute of Atomic Energy NNC RK

11月 2009 - 現在

学歴

PhD in Technical Physics

Shakarim University

9月 2020 - 8月 2023

認定資格
  • Instructor training course Reactor Engineering

    JAEA, Japan

    8月 2018 - 11月 2018

  • Training course for specialists in the field of nuclear energy

    JAEA, Japan

    11月 2012 - 11月 2012

出版物
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.
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.
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.
MAGAZINE ARTICLE