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Research

RESEARCH AREAS

Reactor Safety Analysis Institute of Heat Engineering performs reactor safety analysis of the light water reactors. IHE research team develops models of the reactors and conducts the analysis.

research1

LBLOCA: mass flow rate through the break, 112 from RPV side , 111 from SG side.

The examples of the different accident scenarios using thermohydraulic codes are listed below:

  • Small break loss of coolant accident (SBLOCA)
  • Large break loss of coolant accident (LBLOCA)
  • Main steam line break (MSLB)
  • Steam Generator tube rupture (SGTR)

Institute of Heat Engineering is also active in the reactor analysis during the severe accidents:

  • Some of the potential scenarios are listed below:
  • Core meltdown accidents
  • Loss of offsite power
  • Station blackouts
  • Large radioactive releases

The methodology for these accidents have been created.

research2

Core meltdown accident, reactor type of Peach Bottom.
5049 s: large core degredation, lower bottom of RPV is begining to break

Modeling of physical processes in reactor cores

Desing of a lead fast reactor core with near zero void worth core, poer 300 MWth

Desing of a lead fast reactor core with near zero void worth core, poer 300 MWth

IHE is performing research in the following areas:

  • Neutronic modeling of the lead fast reactor cores design of the fuel rods, control rods and fuel assemblies for light water reactors
  • Fuel cycle modeling

Modeling of physical processes in steam generators

IHE is performing research in the following areas:

Wytwornica pary do reaktora AREVA EPR.

Wytwornica pary do reaktora AREVA EPR.

  • Mathematical modeling of steam generators
  • Modeling of the normal and transient states in steam generators
  • Modeling of the steam generators during steam line break (SLB, steam generator tube rupture (SGTR)
  • Calculation of the forces acting on the structural components of steam generators during normal operation and transients.

 

 

 

 

 

 

 

 

 

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