![Loading...](https://link.springer.com/static/c4a417b97a76cc2980e3c25e2271af3129e08bbe/images/pdf-preview/spacer.gif)
-
Article
Integrity Assessment of RBMK Physical Safety Barriers during Prolonged Station Power-Unit De-Energization
Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop a...
-
Article
Control of Beyond Design Basis Accident in Rbmk with Total Blackout with Prolonged Core Dewatering
A scenario is examined for the development of a beyond design basis accident with loss-of-power for internal needs and functional failures/delays in the actuation of mobile means for emergency cooling RBMK in ...
-
Article
Socrat Code: Evaluation for Modeling the Destruction of RBMK Fuel Channels during Serious Accidents
The SOCRAT computational code was developed and is used for modeling serious accidents at NPP. The present article analyzes the possibility of using the physicochemical models implemented in the SOCRAT code to...
-
Article
Unanticipated Large-Diameter Pipe Rupture Accidents in the RBMK-1000 Circulation Loop with Reactor Emergency Cooling System Failure
The results of calculations of large-diameter pipe rupture accidents in the RBMK circulation loop (pressure header of the main circulation pump, down pipe of the steam drum, and distribution group header) with...
-
Article
Assessment of the Importance of Different Factors for the Delay in Reaching a Serious RBMK Core State with Complete Loss of Power to the Power Unit
The computational results obtained for different scenarios of an accident caused by the loss of all power to a power-generating unit with RBMK and no possibility of restoring power from backup sources (dieselg...
-
Article
Channel reactors as an integral part of nuclear power in Russia
The place and role of channel reactors in nuclear power in our country and the main measures for upgrading and improving the power generating units of nuclear power plants with RBMK reactors are described. It ...
-
Article
Characteristic Features of the Development of Serious Unanticipated Accidents in RBMK Reactors and Approaches to Controlling Such Accidents
The basic structural features of RBMK reactor systems (absence of an overall external protective shell, disintegrating nature of the circulation loop, multichannel nature of the core, positive steam coefficien...
-
Article
Technological and operational properties of steels for welded turbine rotors
Welded turbine rotors are commonly produced from steels 34KhMA and 32KhM1A. Since the unit power of the rotors has increased from 300 to 1200 MW, these steels no longer satisfy the requirements for rotor mater...
-
Article
Role of separate factors in the development of the chernobyl accident
-
Article
An analysis of the dynamics of the RBMK-1000 reactor for rupture of the pressurized collector at low power
-
Article
Testing algorithms for calculating steam-water flow dynamic
-
Article
Analysis of the first phase of the development of the accident in the fourth block of the Chernobyl Atomic Power Station
-
Article
Increasing the safety of atomic power stations with RBMK reactors
-
Article
Enhancement of heat transfer in the RBMK and RBMKP
-
Article
Organizational and technical unification in designing equipment for polyclinic services
-
Article
Operating efficiency of steam separators in power plants with RBMK reactors
-
Article
Strength of weld joints on acceleration models with surface defects
-
Article
Calculation of plane electric fields in channels of magnetohydrodynamic instruments
The local and integral characteristics of flat MHD channels are studied with allowance for longitudinal and transverse edge effects and heterogeneities in the distributions of conductivity and stream velocity....