Results 11 to 20 of about 10,176 (222)
The hydrogen removal system ensures hydrogen safety. At a VVER nuclear power plant, it consists of passive catalytic hydrogen recombiners. The calculation of devices is of great importance for safety justification, since the complex conditions of an ...
V. V. Sorokin
doaj +1 more source
Numerical simulation on heat transfer of VVER core cather
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 +4 more
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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
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 +3 more
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Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent [PDF]
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 +5 more
doaj +1 more source
Nuclear Material Monitoring for the Reprocessing Plant RT-1 at Mayak [PDF]
C
Maenhout, Greet +4 more
core +3 more sources
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 +2 more
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Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000 [PDF]
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
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Наближена оцінка температурного стану керамічного ядерного палива в циліндричних твелах та впливу на нього процесів і параметрів конструкцій активної зони реактора [PDF]
The approximate mathematical model of the temperature state of ceramic nuclear fuels in cylindrical fuel elements was proposed in the form of linear ordinary differential equation and the boundary conditions. The theory of heat conduction and assumptions
Chibisov, Dmytro, Romashov, Yury
core +2 more sources
Расчет градиента температуры перспективного ядерного топлива для реактора типа ВВЭР [PDF]
The paper considers the possibility of using the dispersion of fuel in VVER-1000 reactors.
Чуйкина, Анастасия Владимировна +1 more
core +2 more sources

