Results 181 to 190 of about 705,564 (243)

Modernization of Existing VVER-1000 Surveillance Programs

Journal of ASTM International, 2012
Abstract According to generally accepted world practice, evaluation of the reactor pressure vessel (RPV) material behavior during operation is carried out using tests of surveillance specimens. The main objective of the surveillance program consists in insurance of safe RPV operation during the design lifetime and lifetime-extension ...
V. Kochkin, D. Erak, D. Makhotin
openaire   +1 more source

Extended analysis of VVER-1000 surveillance data

International Journal of Pressure Vessels and Piping, 2002
Abstract Up to now 20 surveillance specimen sets of 14 VVER-1000 Reactor Pressure Vessel (RPV) have been evaluated in Russia, Ukraine and Bulgaria by different testing organisations: • Kurchatov Institute, Russia (10 RPVs); • Institute for Nuclear Research, Ukraine (two RPVs); • Institute of Metal Science, Bulgaria (two RPVs).
A Kryukov, D Erak, L Debarberis, F Sevini, B Acosta   +4 more
openaire   +1 more source

Calculation of “full core” VVER-1000 benchmark

Kerntechnik, 2018
Abstract The 2-D benchmark related to the “full-core” of VVER-1000 was proposed at the AER working group A&B meeting in 2015. Such type of benchmarks requires the adequate specification of the volume surrounding the core where geometry is complex enough.
S. S. Aleshin, A. S. Bikeev, D. S. Oleynik, A. I. Shcherenko   +3 more
openaire   +1 more source

Enhanced VVER-1000 Fuel Technology and Performance

Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 2009
The United States Department of Energy, through the Pacific Northwest National Laboratory (PNNL), provides management and technical support for the International Nuclear Safety Program (INSP) to improve the safety level of VVER-1000 nuclear power plants in Central and Eastern Europe.
H. Shah, R. Latorre, G. Raspopin, J. Sparrow   +3 more
openaire   +1 more source

VVER-1000 Model Assessment Using RELAP5-3D

Nuclear Technology, 2005
Detailed thermal-hydraulic analysis of commercial power reactors requires modeling of complex multidimensional thermal, fluids, and neutronic behavior. One code that has three-dimensional (3-D) thermal-hydraulic and neutronic capabilities is RELAP-3D.
Emilian L. Popov, Graydon L. Yoder, Valeri Velichkov   +2 more
openaire   +1 more source

VVER 1000 Severe Accident Analyses Using MELCOR Code

Journal of Nuclear Engineering and Radiation Science, 2019
This work describes the computer model development of the water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and its subsequent use for the accident scenarios analysis leading to the core melting.
Marek Ruščák, Guido Mazzini, Milos Kynčl, Sevastyan Savanyuk, Miroslav Hrehor, Alis Musa, Alain Flores y Flores   +6 more
openaire   +1 more source

Neutronic study of nanofluids application to VVER-1000

Annals of Nuclear Energy, 2010
Abstract The change in neutronic parameters of the VVER-1000 nuclear reactor core attributable to the use of nanoparticle/water (nanofluid) as coolant is presented in this paper. Optimization of type and volume fraction of nanoparticles in water that affect the safety enhancement of core primary parameters is intended in this study. Reactivity change,
K. Hadad, A. Hajizadeh, K. Jafarpour, B.D. Ganapol   +3 more
openaire   +1 more source

Comparative analysis and modeling safe variability areas of power for VVER-1000 and AP-1000 power units

IOP Conference Series: Earth and Environment
We conducted an analysis of the safe loading and power maneuvering areas for both existing VVER-1000 power units and prospective AP-1000 power units. Mathematical models were developed to represent these areas accurately.
Ye Saukh, O. V. Godun
semanticscholar   +1 more source

Automatic Modeling of VVER-1000 Power Maneuvers

Atomic Energy, 2018
A special version of the IR code is described. The purpose of this code is to generate recommendations for the reactor operator when operating in a maneuvering regime, automate boron regulation, and study the maneuvering characteristics of VVER-1000 fuel loads.
openaire   +1 more source

SEARCHING FOR THE BOUNDARIES OF REPRESENTATION OF INTERNAL DISTURBANCES OF THE VVER-1000 CORE IN THE FORM OF PHYSICAL-MATHEMATICAL AND APPROXIMATION MODELS

ELECTRICAL AND COMPUTER SYSTEMS
. The scientific article is devoted to the study of the use of physical-mathematical and approximation models for simulation of the power change control system at nuclear power plants with VVER-1000.
T. Petik, M. Lobachev
semanticscholar   +1 more source