psb-vver

THERMO-HYDRAULIC TEST FACILITY-MODELS OF
WATER-COOLED REACTORS (PSB-VVER)
JSC «EREC» offers carrying out of tests on studying of thermohydraulic phenomena of water-cooled reactors during design basis
and beyond design basis accidents as well as during transient regimes.
It can be done using the PSB-VVER Test facility.
DESCRIPTION
The PSB VVER Test Facility is a large scale integral installation,
of the primary circuit of NPP with VVER –1000/1200. It consists of
four loops, connected to a model of the reactor. Each loop includes
a circulation pump, a steam generator, «cold» and «hot» pipelines.
One of the loops is equipped with special nozzles for connection
to the primary circuit loss of coolant accidents (LOCA) imitation
system. The Test Facility also includes pressurizer and models of the
active and passive safety systems.
The reactor model consists of four elements – external downcomer,
core model, core bypass and upper plenum. The core model is a
bundle of fuel elements imitators (168 of those), with indirect heating
with electric power up to 10 MW.
The Test Facility is equipped with the modern data aquisition
system (DAS) and I&C system. The DAS includes 1000 measurement
channels with sampling frequency of 20 Hz and 16 channels with
sampling frequencies up to 1000 Hz. The Test Facility is equipped
with the devices for measuring coolant temperature, pressure and
differential pressure, void fraction, coolant flow rate, voltage, current
and power.
Joint Stock Company
«Electrogorsk Research and Engineering Center
on Nuclear Power Plants Safety»
(JSC «EREC»)
MAIN TECHNIQUE CHARACTERISTICS
Coolant ........................................................................... water
Power and volume scaling factor ....................................... 1:300
Elevation scaling factor ..................................................... 1:1
Primary circuit:
Pressure ........................................................................... up to 18 MPa
Coolant temperature ......................................................... up to 350 °C
Coolant flow through the simulated fuel element bundle ... up to 280 t/h
Secondary circuit:
Pressure ........................................................................... up to 13 MPa
Temperature .................................................................... up to 320 °C
Feed water flow per SG ..................................................... up to 5 t/h
The cost of works on Test Facility is defined depending on the
requirement specification of the Customer.
Contact person
Melikhov Oleg Igorevich
Tel. (496 43) 3-15-45, E-mail: [email protected]
St. Constantine str., 6, Electrogorsk,
Moscow Region, 142530 Russia
32
JSC «EREC», Saint Constantine st., 6
Electrogorsk, Moscow region, 142530, Russia
E-mail: [email protected]; http://www.erec.ru
phone: +7 (49643) 3-30-74 , fax: +7 (49643) 3-12-35

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