Results 81 to 90 of about 4,383 (200)
Depletion calculation of VVER 1000 reactor fuel using KENO code
The introduction to operational nuclear reactors focusing on light-water pressurized reactor VVER 1000 is in the beginning of this Master´s thesis. This thesis covers basic technology of VVER 1000 reactor with focus on reactor core and nuclear fuel TVSA ...
Janošek, Radek
core +1 more source
Interactive nuclear plant analyzer for VVER-440 reactor [PDF]
This document discusses an interactive nuclear plant analyzer (NPA) which has been developed for a VVER-440, Model 213 reactor for use in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis
Shier, W., Horak, W., Kennett, R.
core +1 more source
Realizing a deep reinforcement learning agent for real-time quantum feedback. [PDF]
Reuer K +12 more
europepmc +1 more source
Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometries
In the framework of the EU Horizon 2020 McSAFE project, a Serpent2-SUBCHANFLOW coupling has been developed with the aim at performing large-scale pin-by-pin depletion and transient calculations in Light Water Reactors.
Imke, Uwe +9 more
core +1 more source
Improved Passive Gamma Emission Tomography image quality in the central region of spent nuclear fuel. [PDF]
Virta R +5 more
europepmc +1 more source
Benchmarks and test facilities of VVER reactors
The aim of this bachelor’s thesis is to describe the topic of benchmarks and test facilities for pressurized water reactors of the eastern concept VVER type.
Šimek, Ondřej
core +1 more source
An analysis of the “Fast” noise measurements of the dynamic VVER processes [PDF]
Studies of maneuverable modes of VVER to confirm the possibility of participation of nuclear power plants in the mode of daily carrying capacity have been conducted for quite a long time. Tests at various nuclear power plants with VVER-1000 (Zaporizhzhia
Gennady V. Arkadov +2 more
doaj +3 more sources
ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
In 2016 a new version of code ANDREA for core design and reload safety analysis of VVER reactors has been released. The new code version includes several major improvements.
J. Hejzlar +3 more
core +1 more source
Calculation of VVER MOX pin-cell benchmark with OpenMC code
This article presents the results of the 'Weapons-Grade MOX VVER-1000 Neutronics Benchmarks' calculated with the OpenMC code. The purpose of this work was to master the OpenMC code and adapt it for VVER calculations in order to use it in the research ...
Bahdanovich, R., Nikalaichyk, A.
core +1 more source
Positron Annihilation Study of RPV Steels Radiation Loaded by Hydrogen Ion Implantation. [PDF]
Slugen V +6 more
europepmc +1 more source

