Results 1 to 10 of about 688 (173)

Numerical simulation on heat transfer of VVER core cather

He jishu, 2023
BackgroundThe core corium may melt through the reactor pressure vessel wall then lead to the failure of the second barrier during a serious accident. Core catcher can collect and cool the corium and prevent the development of severe accident.PurposeThis ...
ZHU Guangyu, GUO Chao, LIU Qiaofeng, LI Chun, YI Yan   +4 more
doaj   +1 more source

Autonomous Thermosiphon System of Passive Residual Heat Removal from the Primary Circuit of the Reactor Plant: Features of Operation, Characteristics and Basic Advantages

Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика, 2023
An autonomous system of passive removal of residual heat (PRRHS) of a reactor installation with VVER designed to ensure the safety of nuclear power plants in an accident with complete long-term blackout is considered.
I. I Sviridenko, D. V. Shevelyov
doaj   +1 more source

Accounting of the vver-1200 overload influence for fission products activities calculating

Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук, 2020
Current work is aimed at the analysis of the fission products decay influence during fuel reloading, when calculating the accumulated fission products activity for the VVER-1200 reactor fuel campaign. The Bateman problem solution based technique was used
A. M. Petrovski, T. N. Korbut, E. A. Rudak, M. O. Kravchenko   +3 more
doaj   +1 more source

Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent [PDF]

Ядерна фізика та енергетика, 2023
To calculate radiation fields in the concrete biological shield (CBS) of the VVER-1000 reactor in this work, we have developed and applied the Monte Carlo code Serpent simulation framework based on the variance reduction technique. We have quantified the
O. M. Khotiaintseva, O. R. Trofymenko, V. M. Khotiaintsev, A. V. Nosovskyi, S. E. Sholomytsky, V. I. Gulik   +5 more
doaj   +1 more source

The problem of minimizing the radioactive leakage into the VVER circuit under normal conditions

Trudy Odesskogo Politehničeskogo Universiteta, 2017
According to the Strategic Energy Technologies plan, two priorities have been accepted by the European Commis-sion: develop and strengthen energy-efficient systems; increase safety in the use of nuclear energy.
Сергій Миколайович Пелих, М. О. Фролов, А. В. Наливайко, Чжоу Хуійю   +3 more
doaj   +7 more sources

Potential and possibility of extending the campaign to increase VVER-1000 power units on sliding distribution of the secondary circuit

Глобальная ядерная безопасность, 2023
The paper considers the efficiency and possibility of implementing into the operational practice of VVER-1000 power units the campaign extension mode at the sliding pressure of the second circuit.
A. S. Grachev, A. A. Lapkis, A. Yu. Smolin   +2 more
doaj   +1 more source

Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000 [PDF]

Ядерна фізика та енергетика, 2023
The article presents the results of the numerical simulation of the signal formation process of the background wires of self-powered neutron detectors (SPND) under the action of gamma radiation in the VVER-1000 core using MCNP code. The validation of the
V. I. Borysenko, V. V. Goranchuk
doaj   +1 more source

Prospects of creation of the two-component nuclear energy system [PDF]

Nuclear Energy and Technology, 2019
Possible options of organization of two-component energy system with closed nuclear fuel cycle (CNFC) and new business potential associated with provision of CFC services to foreign customers are examined.
Andrey Yu. Petrov, Alexander V. Shutikov, Nikolay N. Ponomarev-Stepnoy, Valery S. Bezzubtsev, Mikhail V. Bakanov, Vladimir M. Troyanov   +5 more
doaj   +3 more sources

Possible in-service damages of steam generators at VVER-1000 and VVER-1200 NPP units and their impact on long-term operation [PDF]

E3S Web of Conferences, 2020
Specific features of corrosion-mechanical damages of primary circuit header to steam generator vessel branch welds at VVER-1000 NPPs and their impact on safety and economic efficiency during long-term operation are analysed. Measures to avoid the damages
Arzhaev Alexander, Arzhaev Alexey, Makhanev Valentin, Antonov Mikhail, Emelianov Anton, Kalyutik Aleksander, Karyakin Yury, Kurakin Maksim, Lyashenko Daniil, Arzhaev Kirill, Denisov Ilya   +10 more
doaj   +1 more source

Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC [PDF]

MATEC Web of Conferences
Nuclear power is a reliable and large-scale source of GHG-free electricity. This study asses the viability of ATF fuel of uranium nitride (UN) and uranium carbide (UC) as fuel for the VVER-1200 reactor.
Jamil Meekal, Ali Majid
doaj   +1 more source