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Steam Generator Tube Integrity Facilities

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Steam Generator Tube Integrity Facilities

The Nuclear Engineering Division conducts research and development and validates models for tube performance in pressurized water reactor steam generators.


 

The Steam Generator Tube Integrity Facilities include:

High Temperature Blowdown Facility:

The facility provides a high flow rate of 400 gpm at pressures up to 3000 psi for reasonable test times at temperatures up to 343?C and prototypical single-phase pressurized water flow conditions inside the tube.

High Temperature Blowdown Facility: provides a high flow rate (400 gpm) at pressures up to 3000 psi at temperatures up to 343°C.

High Temperature Blowdown Facility: provides a high flow rate (400 gpm) at pressures up to 3000 psi at temperatures up to 343°C.
Tube Containment Test Module

High Temperature Blowdown Facility: provides a high flow rate (400 gpm) at pressures up to 3000 psi at temperatures up to 343°C.
Click on each photo to view a larger image.

Room Temperature High Pressure Facility:

Permits the unstable bursting of tubes that cannot be failed at 3000 psi in the High Temp Blowdown Facility allowing assessment of safety margins.
Two stage testing is used to maximize information because flaws can undergo considerable ligament tearing and leakage at pressures lower than that at which unstable burst occurs. Tests conducted to characterize single and multiple axial/circumferential notch opening pressures, data for orifice leak model development, influence of pressurization rate on flaw rupture and others.

Room Temperature High-Pressure FacilityRoom Temperature High-Pressure Facility.
Click on photo to view a larger image.

Tube/Tube-sheet Severe Accident Leakage Facility:

Tests planned in this facility will address the hydraulic aspects of severe accidents by developing a leak rate model from leak rate tests conducted at room temperature and at 700?C.

Tube/Tube-sheet Severe Accident Leakage FacilityTests address hydraulic aspects experimentally by developing a leak rate model from leak rate tests conducted at room temperature and at 700°C.
Click on photo to view a larger image.

Model Boiler Facility:

The facility provides more prototypical conditions than those obtained in isothermal autoclave or electrically heated crevice test systems.  The test conditions can match both the tube wall temperature and crevice heat flux conditions with the prototype.  The facility uses a two-chamber pressure vessel (primary/secondary) and a dedicated computer data acquisition system to develop data under precise conditions.

Model Boiler FacilityModel Boiler Facility: Tests conducted to develop an improved understanding of the interplay between tube heat transfer, crevice geometry, and chemical hideout.
Click on photo to view a larger image.

Last Modified: Thu, February 13, 2014 3:37 PM

 

RELATED RESOURCES

Research

  • Steam Generator Tube Integrity Program
    Steam generator tubes, which account for more than 50% of the primary pressure boundary surface of PWRs, have experienced in-service corrosive and mechanical degradation of various forms since the beginning of PWR commercial operation in the late 1950s...

Capabilities

For more information:

Corrosion and Mechanics of Materials
Sect. Manager: K. Natesan

K. Natesan's Executive Bio

 

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