design and engineering pilot studies deliveries simulations process development certification testing. ICEO. pilot cogeneration plant servicing

Power equipment testing center


Contacts:


Head of the Power Equipment Test Center (ICEO), PhD in Technical Sciences Scheglov Andrey Anatolyevich

tel: 8 (812)  578 8812, 8 (812) 578 8809

The enterprise has its own Power Equipment Testing Center (ICEO), which was certified by the Federal Certification Agency of the Russian Federation and the State Atomic Energy Corporation Rosatom.

 JSC "NPO CKTI" has also confirmed its competence as a testing laboratory (center) in the INTERGAZSERT system.



Main activities of the Department

  • Conducting tests (acceptance and approval tests, qualification tests, routine tests, certification tests, type tests, thermohydraulic tests, etc.) of power generating equipment.
  • Tests of valves, heat exchange and other equipment for NPP.
  • Marine valving tests.
  • Tests of valves and other equipment for the oil and gas industry.
  • Tests of recirculation coolers, recirculation ventilation plants, air conditioners and other finned-tube heat exchangers.
  • Tests of gasketed plate heat exchangers.
  • Tests of brazed plate heat exchangers (of Compabloc type).
  • Tests of plate and shell heat exchangers.
  • Tests of tube and shell heat exchangers.
  • Pump tests.
  • Drive tests.
  • Experimental research of thermohydraulic processes and hydrodynamic stability at a large-scale model of natural circulation circuit for LNPP-2 (Leningrad Nuclear Power Plant 2) of afterheat removal passive system through the steam generator(ARPS PG).
  • Experimental evaluation of hydraulic and cavitation behaviour of valves.
  • Development of programs and procedures for thermal hydraulic tests of heat exchanging equipment.
  • Development of thermohydraulic calculation software for heat exchanging equipment.
  • Conducting heat, hydraulic and aerodynamic design procedures for heat exchanging equipment and pipeline valves.
  • Tests of equipment included in main steam valve units of nuclear power plants and other products which must comply with nuclear power safety requirements.





  • Main steam isolation valve NI.006 for the first unit of LAES-2. DN = 600 mm; Pop = 7 MPa; Top = Тr = 286 °C ; height 3.5 m; weight 10 t

    Isolation valve NT.001 for the first unit of LAES-2. DN = 400/300 mm; Pop = 7.5 MPa; Top = Тr = 293 °C ; height 2 m; weight 4.2 t

    Main safety valve Р59504-450. DN = 300/400 mm; Pop = 8.5 MPa; Top = Тr =300 °C ; height 2,5 m; weight 4.5 t

    Pilot-operated safety valve of pressurizer DN 100 UF50024-100-15 with additional control line for LAES-2

  • Marine valving tests.

  • Straight-through shut-off valve with single-cavity drive and manual control

    Bellows-operated angle-type isolation valve IUKL.492244.026
    492244.026

    Клапан с пневмоприводом типа ЗЗТ С965

  • Oil and gas valving tests.

  • Ball valve DN 300, PN 10 MPa

  • Tests of recirculation cooling units, recirculation ventilation plants, air conditioners and other corrugated-pipe heat exchangers.







  • Recirculation ventilation plant RUB-60 for the Novovoronezhsk Nuclear Power Plant-2



    Recirculation cooling plant RCP-6.3 EMK.0155.000.00.000 for the third unit of the Rostov Nuclear Power Plant (emergency mode emulation)

  • Tests of dismountable plate heat exchangers.

  • Heat exchangers NT150 SH/CD-16/15 and NT100 THV/CDL-10/15 for the Belarus Nuclear Power Plant

  • Tests of brazed plate heat exchangers.


  • FPB 025 type heat exchanger for LAES-2

  • Tests of plate and shell heat exchangers.

  • Gas blow-off processing system heat exchanger KKS 10KPL11AC002 with a stack of brazed plates Plate Stack XPSP 50 for the Belarus Nuclear Power Plant

  • Tests of tube and shell heat exchangers.

  • Test research of thermohydraulic processes and hydrodynamic stability at a large-scale model of natural circulation circuit for LAES-2 (Leningrad Nuclear Power Plant 2) that passively removes heat through the steam generator (SPOT PG).

     




  • Large-scale model SPOT PG of the reactor unit LAES-2. Coolant heat capacity and power scale (1:110)

    1 – steam generator/separator

    2 – circulation pump

    3, 7 – throttling flow meters

    4, 5 – electric heaters

    6 – main steam isolation valve

    8 – steam pipeline

    9 – condensate pipeline

    10 – emergency cooling heat exchanger

    11 – emergency heat removal tank

  • Experimental determination of the hydraulic and cavitation characteristics of the valves.





  • The main safety valve of the head sample of the pilot-operated safety valve of the steam generator ND.002 for LNPP-2



    Shut-off valve (OK) NT.001 for LNPP

  • Conducting heat, hydraulic and aerodynamic design procedures for heat exchanging equipment and valving.

  • Development of thermohydraulic design software for heat exchanging equipment.

     


  • Screenshots of spiral case PVD recalculation software developed on request by NPO CKTI JSC.

Test rigs of the Center.

The department has a large and unique experimental facility.

Test rig KS10606

  • Bench of 37 m high, with an area of 12x33 m².
  • Two own electrically heated installations for the superheated steam generation with a pressure of up to 20 MPa at a temperature of up to 570°C.
  • Air compressor for pressure up to 40 MPa.
  • High design parameters of the installed equipment (P=32 MPa, t=600°C):
  • circulation contour of 30 m high;
  • circulation and feed pumps with flowrate control (up to 6 kg/s);
  • electric heaters with a total capacity of up to 8 MW;
  • Pressure compensators.
  • Heat-exchange units.
  • A steam temperature of up to 600°C is possible with individual models, Modern system of measuring and collecting information.



Control panell of the Complex Test Rig KS10606



On of the testing spots of the Complex Test Rig KS10606 BZOK-600 and IPU PG are put on the test rig