Results 11 to 20 of about 648 (179)

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

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

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

Radiocarbon Measurements Reveal Underestimated Fossil CH4 and CO2 Emissions in London

Geophysical Research Letters, Volume 50, Issue 15, 16 August 2023., 2023
Abstract Radiocarbon (14C) is a powerful tracer of fossil emissions because fossil fuels are entirely depleted in 14C, but observations of 14CO2 and especially 14CH4 in urban regions are sparse. We present the first observations of 14C in both methane (CH4) and carbon dioxide (CO2) in an urban area (London) using a recently developed sampling system ...
Giulia Zazzeri, Heather Graven, Xiaomei Xu, Eric Saboya, Liam Blyth, Alistair J. Manning, Hannah Chawner, Dien Wu, Samuel Hammer   +8 more
wiley   +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

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal‐Hydraulic System Analysis Code

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
wiley   +1 more source

Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland

Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023
This paper introduces the utilization of the International Atomic Energy Agency’s toolkit for reactor technology assessment (RTA) application to deploy small modular reactors (SMRs) in the Czech Republic, Egypt, and Poland. The increasing demand for clean energy has led to the prominence of small modular reactors (SMRs) in addressing global energy ...
Waad Saleh, Dalibor Kojecky, Edyta Agata Macieja, Juyoul Kim, Leon Cizelj   +4 more
wiley   +1 more source