Test Rigs for Physical, Thermal & Hydrodynamic
Tests of Nuclear Reactors
1. The "PRM" Power Reactor Model
This facility is intended for experimental research
on effects of thermal and hydraulic parameters of the coolant
upon nuclear physical parameters of the reactor core, and to determine
characteristics of the reactor core using its sub-critical component.
Main characteristics:
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coolant pressure
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up to
1.6·107 N/m2
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coolant maximum temperature
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450oС
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coolant flow rate through 3 electrically heated channels
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up to 10 t/hr,
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heat release in 3 channels
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up to 6·105W
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feed water pressure
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up to
6·106 N/m2
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feed water flow rate
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up to2 t/hr
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2. The "G-1" Critical Assembly for
Research on Nuclear Physical Characteristics of Various Types
of Reactor Cores, Including with High-temperature Gas Cooling
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The test facility includes:
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a critical assembly
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control and protection systems
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a monitoring & measurement system
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a hardware control system
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a data acquisition & analysis system
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a power supply system
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a radiation monitoring system
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a support system
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relevant rooms, including a shielded box
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