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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. (see larger size 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 Facility

Room Temperature High Pressure Facility (see larger size 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 Facility

Tests address hydraulic aspects experimentally by developing a leak rate model from leak rate tests conducted at room temperature and at 700°C. (see larger size 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 Facility

Model Boiler Facility: Tests conducted to develop an improved understanding of the interplay between tube heat transfer, crevice geometry, and chemical hideout. (see larger size image)

Contact:
Engineering Development & Applications Department
Corrosion and Mechanics of Materials
Sect. Manager: K. Natesan
Fax: +1 630-252-3604

Resources

RELATED RESEARCH

Steam Generator Tube Integrity Program

  • 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... [more]

RELATED NE FACILITIES

About the Department

Contact

K. Natesan
Corrosion and Mechanics of Materials
Fax: +1 630-252-3604


ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division
9700 South Cass Ave., Argonne, IL 60439-4814
A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC
 

Last modified on September 11, 2009 18:49 +0200