Results 81 to 90 of about 705,564 (243)

Methodology of Fuel Burn Up Fitting in VVER-1000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations

EPJ Web of Conferences, 2016
Paper describes the new approach of fitting axial fuel burn-up patterns in peripheral fuel assemblies of VVER-1000 type reactors, on the base of ex-core neutron leakage measurements, neutron-physical calculations and in-core SPND measured data.
Borodkin Pavel, Borodkin Gennady, Khrennikov Nikolay   +2 more
doaj   +1 more source

PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR

Acta Polytechnica CTU Proceedings, 2016
The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic system code (TRACE) for ...
Marek Ruščák, Guido Mazzini
doaj   +1 more source

An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly

Ядерна фізика та енергетика, 2016
Considering the fuel assembly (FA) load history and the nonuniformity of energy release for the fuel elements (FEs) contained in this FA, a method for forecasting of probability of VVER-1000 FE cladding failure due to FE cladding deformation damage ...
S. N. Pelykh, M. V. Maksimov, S. D. Ryabchikov   +2 more
doaj  

Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode

Alexandria Engineering Journal, 2018
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar, M. Jabbari, M. Khaleghi, M. Hashemi-Tilehnoee   +3 more
doaj   +1 more source

17. Issues for Nuclear Power Plants Steam Generators [PDF]

, 2011
Open Access ...
Bonavigo L., De Salve M.
core  

Nuclear Energy Complexes: Prospects for Development and Cooperation [PDF]

1. 2005–2006 was a critical period in the development of the nuclear complexes of Russian Federation and the Republic of Kazakhstan. These years have ushered in a “nuclear renaissance”.
Vinokurov, Evgeny
core   +1 more source

Nuclear Safety Evaluation in Steam Generators [PDF]

, 2014
Import 05/08/2014Tato bakalářská práce se zabývá hodnocením všech typů parogenerátoru a porovnání jejich základních parametrů s ohledem na jadernou bezpečnost. V prvních kapitolách jsou popsány parametry určitých parogenerátorů. Dále je přiblížen samotný
Vobořil, Martin
core  

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility

Science and Technology of Nuclear Installations, 2012
The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000.
A. Del Nevo, M. Adorni, F. D'Auria, O. I. Melikhov, I. V. Elkin, V. I. Schekoldin, M. O. Zakutaev, S. I. Zaitsev, M. Benčík   +8 more
doaj   +1 more source

OPTIMIZATION OF POWER LOAD FOLLOWING MODES FOR VVER-1000

POWER ENGINEERING: economics, technique, ecology
  The need to involve nuclear power plants in daily power regulation is driven by the gradual increase in the share of renewable energy sources in the Unified Energy System (UES) of Ukraine. Additionally, the conditions for implementing measures to address climate change and deteriorating operating conditions of the UES in the face of economic changes
Svyatoslav Kobrynchuk, Maksym Ieremenko
openaire   +2 more sources

Calculation of static characteristics of linear step motors for control rod drives of nuclear reactors-an approximate approach [PDF]

, 1993
This paper describes an approximate method for calculating the static characteristics of linear step motors (LSM), being developed for control rod drives (CRD) in large nuclear reactors.
Ivanov, A., Khan, S.
core