Results 11 to 20 of about 1,019,583 (175)

VVER-1000 reactor model using the Serpent 2 code for core power distribution calculation [PDF]

Ядерна фізика та енергетика, 2023
A VVER-1000 reactor model using the Monte Carlo Serpent 2 code for core power distribution calculation is presented. The core and zones located near to the core were modeled in detail, without simplification.
V. V. Ilkovych
doaj   +2 more sources

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

Journal 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, Nikolay I. Geraskin, Vladimir A. Apse, Vasily B. Glebov, Gennady G. Kulikov, Evgeny G. Kulikov   +5 more
doaj   +2 more sources

Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools [PDF]

Science and Technology of Nuclear Installations, 2010
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez, W. Jaeger, M. Boettcher, B. Truong   +3 more
doaj   +2 more sources

Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4 [PDF]

Nukleonika, 2014
One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors.
Saadatian-derakhshandeh Farahnaz, Safarzadeh Omid, Shirani Amir Saiid   +2 more
doaj   +3 more sources

Accident Management in VVER-1000 [PDF]

Science and Technology of Nuclear Installations, 2008
The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose
F. D'Auria, A. Suslov, N. Muellner, G. Petrangeli, M. Cherubini   +4 more
doaj   +2 more sources

CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vessel [PDF]

Annals of Nuclear Energy, 2023
This study presents a code-to-code and model-to-model comparison of coolant mixing in the VVER-1000/V320 Kozloduy Unit 6 nuclear power plant using Computational Fluid Dynamics (CFD). Four different CFD codes were used to simulate coolant mixing in the reactor vessel, namely ANSYS Fluent, ANSYS CFX, TrioCFD, and STAR-CCM+.
Böttcher, M, Bernard, O, Mas, A, Sanchez, V, Nop, R, Belaunde, F, Bourcier, C, Ruban, D, Hashymov, A, Halim, Ossama, Pucciarelli, A, Forgione, N   +11 more
core   +8 more sources

Assessment of the possibility for large-scale 238Pu production in a VVER-1000 power reactor [PDF]

Nuclear Energy and Technology, 2023
The paper presents the estimates for the possibility for large-scale production of 238Pu in the core of a VVER-1000 power reactor. The Np-fraction of minor actinides extracted from transuranic radioactive waste is proposed to be used as the starting material. The irradiation device with NpO2 fuel elements is installed at the reactor core center.
Shmelev,Anatoly, Geraskin,Nikolay, Apse,Vladimir, Kulikov,Gennady, Kulikov,Evgeny, Glebov,Vasily   +5 more
openaire   +7 more sources

Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit [PDF]

, 2020
At the moment, 11 nuclear power plants (NPP) are under operation in the Russian Federation. More than half of the reactor units used are VVER-1000 reactors. NPP is a complex engineering structure consisting of plenty of complex equipment. Equipment operates under severe conditions: hard radiation, high temperatures, and high pressure.
Ovsenev, Alexander Evgenievich, Permikin, Anton Andreevich, Balachkov, Maxim Mikhailovich, Belyavskiy, S. V.   +3 more
openaire   +2 more sources

Crucible-type core catcher for VVER-1000 reactor

, 2005
For new designs of NPPs with VVER-1000 reactors a crucible-type core catcher has been developed to stabilize and cool down molten corium in the reactor pit.
Berkovich, V.M.,, Bechta, Sevostian,, Svetlov, S.V.,, Zagryazkin, V.M.,, Strizhov, V.F.,, Khabensky, V.B.,, Kisselev, A.E.,, Sidorov, A.S.,, Gusarov, V.V.,, Asmolov, V.G.,, Bezlepkin, V.V.,, Granovsky, V.S.,, Kukhtevich, I.V.,   +12 more
core   +8 more sources

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