Results 61 to 70 of about 375 (173)

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

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

open access: yesActa 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

open access: yesЯдерна 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   +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

open access: yesAlexandria 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   +3 more
doaj   +1 more source

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

open access: yesEPJ 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   +2 more
doaj   +1 more source

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

open access: yesScience 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   +8 more
doaj   +1 more source

Vanquishing the computational cost of passive gamma emission tomography simulations leveraging physics-aware reduced order modeling. [PDF]

open access: yesSci Rep, 2023
Cavallini N   +7 more
europepmc   +1 more source

Sorting of surveillance specimen halves relative to their location in the VVER-1000 reactor under irradiation

open access: yesЯдерна фізика та енергетика, 2019
The paper presents the procedure developed at the Department of Radiation Material Science of INR NAS of Ukraine for longitudinal radiometric scanning of surveillance specimens of the Ukrainian reactor vessels and its joint application with ...
Yu. S. Gulchuk, L. I. Chyrko
doaj   +1 more source

Localizing Perturbations in Pressurized Water Reactors Using One-Dimensional Deep Convolutional Neural Networks. [PDF]

open access: yesSensors (Basel), 2021
Pantera L   +8 more
europepmc   +1 more source

Structural and Parametric Optimization of S-CO2 Nuclear Power Plants. [PDF]

open access: yesEntropy (Basel), 2021
Rogalev N   +4 more
europepmc   +1 more source

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