Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Integral Behavior of the Atlas Facility for a 3-inch Small Break Loss of Coolant Accident

Over the past 30 years, several large integral facilities have been utilized in order to understand transient behavior in nuclear power plants. The main objective of these integral facilities was to enhance our physical understanding of transient phenomena during LOCA or non-LOCA transients. An integral database was also used as a basis for the development and verification of thermal hydraulic ...

Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions

Reactor Pressure Vessel Embrittlement—i

Evaluation of Single Failure Effects During Loss of Coolant Accidents For A VVER-440 Reactor

This paper describes the results of an analysis of loss of coolant accidents (LOCA's) for the Soviet designed, light water cooled and moderated reactors referred to as VVERs. The VVER unit selected for this analysis is designated as VvER-440 Model 213. This plant generates 440 Mwe and is of current interest since meen are now operating and additional units are in various stages of construction ...

Detailed Cfx-5 Study of the Coolant Mixing within the Reactor Pressure Vessel of a Vver-1000 Reactor during a Non-symmetrical Heat-up Test

As part of the reactor dynamics activities of FZK/IRS, the qualification of a detailed 3D CFD model of a reactor pressure vessel is a key step in safety evaluations for improving predictive capabilities and acceptability of commercial CFD tools in reactor physics. The VVER-1000 Coolant Transient Benchmark, initiated by OECD, represents an excellent opportunity for validation. In this work a CFD...