#0564Temperature of Water-cooled Reactor

Methodological Security of Temperature Measurement and Diagnostics within Power Water-moderated Water-cooled Reactor (PWR) Type on Base of Analysis of Influence Functions for Measuring Means.

#0939Catcher for the Molten Core

Design of a Catcher for the Molten Reactor Core at an NPP on the Basis of Zirconia Concrete

#0941Database on Fission Products Release

Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000

#1679Radiation Safety Thermal-Hydraulic Codes

Verification of Thermal and Hydraulic Codes, Used for Safety Justification of Russian VVER NPPs

#2105Boron Dilution in WWER Reactors

Study of Emergency Situations Related to Boron Dilution in WWER Reactors

#3780Reactor Temperature Control

Modernization of Metrological Security of Reactor Thermometry Taking into Account Quality of Thermal Contact Between Thermocouple and Object and Degradation of its Characteristics at Irradiation

#3936Fuel Assemblies under Severe Accident Conditions

Study of Fuel Assemblies with Boron Carbide Absorber Rods under Severe Accident Conditions in the PARAMETER-SF Tests Series