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National Agency for New Technologies, Energy and Sustainable Economic Development

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VAPORE Facility

Application sectors

EnergyMaterials

Problem to solve

The VAPORE experimental facility is designed to perform thermomechanical and fluid-dynamic tests on components and systems to be installed in nuclear and conventional power plants. VAPORE provides important support to industries operating in the framework of power plant engineering and mechanical and structural components of power generating plants. Actually, it provides access to market opportunities closely depending on the supply of innovative components and systems, to be qualified in actual operating conditions, in compliance with a QA program. Potential users: industries interested in power plant engineering and mechanical and structural components to be installed in the main loops of power plants.

Description

The VAPORE facility is inoperated since 2000, but a refurbishment is planned for completion by 2027. The main component is a full-scale PWR reactor pressurizer (formerly PUN) with a volume of 40 m³ and an operating pressure of 180 bar, equipped with 1.4 MW electrical heaters. Steam can be extracted from the upper section of the pressurizer via either a 10" pipe or a 3" pipe (for reduced flowrates), while liquid can be drawn from the lower section using a 12" pipe. The steam line includes a spherical component as a vapor separator. In both configurations, the fluid passing through the test component is driven by discharge lines to a 400 m³ suppression pool. The current setup supports testing with steam or liquid in separate modes, allowing maximum flowrates of up to 300 kg/s for steam and 600 kg/s for liquid. As part of the planned modernization, the facility may be upgraded to enable testing under controlled two-phase flow conditions.

Innovative aspects and advantages

  • Testing with high liquid flow rates up to 600 kg/s
  • Testing with high steam flow rates up to 300 kg/s
  • Thermofluid-dynamic tests at pressures up to 180 bar

Admissible applications

  • Fluid dynamic testing with adjustable flow rates of steam or saturated liquid
  • Qualification of components for full-scale nuclear and conventional plants
  • Qualification of safety valves, piping, depressurization systems, and steam discharge devices in pools (spargers)
  • Thermomechanical testing

Research group involved

Polidori Massimiliano NUC-ENER-SIC ;Cherubini Nadia NUC-IRAD ;Diamanti Dario NUC-ENER-TEC ;Polidori Massimiliano NUC-ENER-SIC ;Ratto Antonino NUC-IRAD-RNR ;Tiranti Giuliano NUC-IRAD-GAM

Revision date

26-05-2025

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VAPORE Facility