Results 201 to 210 of about 10,176 (222)

Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core

Progress in Nuclear Energy, 2010
Seyed Mohammad Mirvakili, Farshad Faghihi   +1 more
exaly  

Subchannel analysis of nanofluids application to VVER-1000 reactor

Chemical Engineering Research and Design, 2013
Ehsan Zarifi, Gholamreza, Farzad Veysi
exaly  

Short-term strength properties and features of high-temperature deformation of VVER reactor pressure vessel steel 15Kh2NMFA-A within the temperature range 20–1200 °C

Nuclear Engineering and Design, 2019
Vladimir D Loktionov, Егор Терентьев   +1 more
exaly  

The criticality of VVER-1000 mock-up with different H3BO3 concentration

Annals of Nuclear Energy, 2013
Michal Košťál, Vlastimil Juricek
exaly  

From VVER-1000 to VVER-1200: Investigation of the Effect of the Changes in Core

2014
Dwiddar, Mohammed S., Badawi, Alya A., Abou-Gabal, Hanaa H., El-Osery, Ibrahim A.   +3 more
openaire   +1 more source

Neutronics design of VVER-1000 fuel assembly with burnable poison particles

Nuclear Engineering and Technology, 2019
Hoai-Nam Tran, Peng Hong Liem, Hung T.P. Hoang   +2 more
exaly  

Thermal hydraulic analysis of VVER-1000 nuclear reactor with dual-cooled annular fuel using K–ω SST Turbulence model

Annals of Nuclear Energy, 2017
Mohammad Hossein Esteki, GholamReza Ansarifar   +1 more
exaly  

Research on nuclear reactor power control system of VVER-1000 with thermal energy supply system

Energy
磊磊邱, Xinyu Wei
exaly  

A simulation of a steam generator tube rupture in a VVER-1000 plant

Energy Conversion and Management, 2008
Mohammad Reza Nematollahi
exaly  

PACTEL - facility for VVER thermal hydraulics

1994
The PArallel Channel TEst Loop (PACTEL) is a medium scale integral test facility (full height, volumetrically scaled, 1:305) designed to simulate thermal hydraulic phenomena characteristic of the VVER reactors with particular attention to the versions used in Finland.
openaire   +1 more source