Results 71 to 80 of about 705,564 (243)

Project PISA: Phosphorus Influence on Steel Ageing [PDF]

open access: yes, 2008
The integrity of the pressure vessel is vital to the safe operation of a nuclear reactor. It is therefore necessary to monitor or predict the changes in the reactor pressure vessel (RPV) material during operation.
ACOSTA IBORRA Beatriz   +14 more
core  

Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site

open access: yesScience and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley   +1 more source

A Possibility for Large-Scale Production of 238Pu in Light-Water Reactor VVER-1000

open access: yesJournal of Nuclear Engineering, 2022
This paper considers the possibility for large-scale production of plutonium isotope 238Pu in the light-water nuclear power reactor VVER-1000. 238Pu is a unique source of long-term autonomous energy supply in various devices for remote regions of the ...
Anatoly N. Shmelev   +5 more
doaj   +1 more source

Electricity privatisation and restructuring in Russia and Ukraine [PDF]

open access: yes, 2005
This report examines reforms to the electricity and gas industries in Russia and ...
Thomas, Stephen
core  

In-service change in the flexural rigidity of the VVER-1000 fuel assemblies

open access: yesNuclear Energy and Technology, 2016
In-service dimensional stability of the VVER-1000 reactor fuel assemblies (FA) depends to a great extent on their flexural rigidity. A decrease in the flexural rigidity in the process of the FA operation in the reactor may lead to such FA bowing as will ...
S.V. Pavlov
doaj   +1 more source

Multiple usage of thorium-based fuel in a VVER-1000 reactor

open access: yesNuclear Energy and Technology, 2022
This paper considers the use of unconventional fuel in nuclear power reactors, using the example of a VVER-type unit, in order to find out the possibility of saving natural fissile uranium nuclei. Saving fissile uranium is one of the important tasks, the solution of which will give time for the development of a two-component nuclear power industry that
Kazansky,Yury   +2 more
openaire   +2 more sources

Optimization of the self-sufficient thorium fuel cycle for CANDU power reactors [PDF]

open access: yes, 2008
The results of optimization calculations for CANDU reactors operating in the thorium cycle are presented in this paper. Calculations were performed to validate the feasibility of operating a heavy-water thermal neutron power reactor in a self-sufficient ...
Bergelson Boris R.   +2 more
core   +2 more sources

Analysis of the residual strength of the high-capacity centrifugal pump with taking into account the effect of corrosive wear due to long-term exploitation [PDF]

open access: yes, 2019
У даній статті була проведено дослідження для визначення залишкової міцності відцентрового насосу, що працює в понад проектний термін експлуатації в лінії насосів енергоблока АЕС.
Ларін, Олексій Олександрович   +2 more
core   +1 more source

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

open access: yesScience and Technology of Nuclear Installations, 2019
Thermal reactors have been considered as interim solution for transmutation of minor actinides recycled from spent nuclear fuel. Various studies have been performed in recent decades to realize this possibility.
Vinh Thanh Tran   +4 more
doaj   +1 more source

Analysis of calculation of fuel rods for strength under transient and steady-state operating conditions

open access: yesNuclear Materials and Energy
The operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
doaj   +1 more source

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