FAQ
    
    AGREEMENT STATES
    
    Facility Locator
    
    What's New
    
    Site Help
    
    Index A-Z
    
    Contact Us
    
    Email Updates
      
      
      
      
       
      Report a Safety Concern
                  Search
        Nuclear Reactors
  
  Power Reactors
Research & Test ReactorsOperating Reactors
New ReactorsOperator Licensing
Research ActivitiesNuclear Reactor Quick LinksNuclear Materials
  
  Types of Nuclear Materials
Fuel Cycle Facilities
Medical, Industrial, & Academic UsesUranium Recovery
Materials TransportationMaterials Environmental Reviews
National Materials ProgramNuclear Materials Quick LinksRadioactive Waste
  
  Decommissioning of Nuclear Facilities
Low-Level Waste
Waste Incidental to Reprocessing
High-Level WasteUranium Mill Tailings
Low-Level Waste Disposal
High-Level Waste DisposalStorage of Spent Nuclear Fuel
Transportation of Spent Nuclear Fuel
Research ActivitiesRadioactive Waste Quick LinksNuclear Security
  
  Domestic Safeguards
Information Security
Radioactive Material SecurityRequired Reporting for Clearance Holders
Insider Threat Program for Licensees
CybersecurityCriminal History & Firearms Checks
Contact UsPublic Meetings & Involvement
  
  The NRC Approach to Open Government
About Meetings Open to the Public
Conferences & SymposiaDocuments for Comment
NRC Rules and Petitions
Facilitating Stakeholder InvolvementNRC Information Quality Guidelines
Subscribe to E-mail UpdatesCommission Schedule
Public Meeting ScheduleAdjudications (Hearings)
Adjudicatory SubmissionsNRC Library
  
  Basic References
Document Collections
ADAMS Public Documents
Public Document Room
LSN LibraryFOIA & Privacy Act
Photos & Videos
Records Management
Training CoursesFAQ Index
Get Copies of Documents
Withholding of Sensitive Information
Controlled Unclassified Information Program (CUI)Electronic Hearing DocketAbout NRC
  
  The Commission
Organization & Functions
Governing Legislation
Plans, Budget, & Performance
Locations
History
Values
Direction-Setting & Policymaking
Research Activities
Radiation ProtectionFire Protection
Safety Culture
How We Regulate
Emergency Preparedness & Response
Public Affairs
Congressional Affairs
Enforcement
International Programs
State & Tribal ProgramsAlternative Dispute Resolution Programs
Privacy Program
Civil Rights Program
Contact Us
Career Opportunities
Contracting Opportunities
Small Businesses
Grant Opportunities
Generic SchedulesOther Links
  
  FAQ
Glossary
Facility Locator
What's NewSite Help
Index A-Z
Contact Us
Email UpdatesNRC Facebook
NRC Twitter Feed
NRC Linkedin
NRC Youtube Channel
NRC Flickr Gallery
NRC Blog Archived
NRC Email Subscriptions - GovDelivery Home
          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC ContractorsResults From Pressure and Leak-Rate Testing of Laboratory-Degraded Steam Generator Tubing (NUREG/CR-6789)

On this page: Publication Information AbstractDownload complete document NUREG/CR-6789 (PDF - 7.57 MB)Publication Information **Manuscript Completed:** November 2001**Date Published:** November 2002 **Prepared by:** K. Kasza, S. Majumdar, I. Park, J. Franklin Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439 J. Davis, NRC Project Manager **Prepared for:** Division of Engineering Technology Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission****Washington, DC 20555-0001 NRC Job Code W6487 Availability Notice Abstract This report presents experimental results obtained from the pressure and leak-rate testing on laboratory-degraded steam generator (SG) tubes. This work Is part of the NRC sponsored Steam Generator Tube Integrity Program. Two tube test facilities were built to carry out the tests. One is the High-Temperature Pressure and Leak-Rate Test Facility (temperatures up to 343°C [650°F], pressures of up to 21 MPa [3000 psi], and pressurized-water flow rates up to 1520 L/min [400 gpm]) for.conducting tube failure and leak-rate tests under prototypic SG operating conditions. The other is the Room-Temperature High-Pressure Facility (pressures up to 52 MPa [7,500 psi] and flow rates up to 48.4 L/mln 112.8 gpm]) capable of testing at pressures associated with overpressure safety margins. The report includes information on flawed-tube testing protocols for tests with or without Internal bladders, the validity of simple orifice flow models for the prediction of flow rates from flaws, and a large data base containing failure pressures and leak rates for machined and stress corrosion cracking (SCQ) flaws produced In the laboratory. 
      
      Page Last Reviewed/Updated Wednesday, March 24, 2021  Home
NEWS RELEASES

EVENT REPORTS

ADAMS

OPEN GOV

DIGITAL GOVERNMENT

THE STUDENT CORNER

PHOTOS & VIDEOS

FOR DEVELOPERS
        About Us
STRATEGIC PLAN

BUDGET & PERFORMANCE

AGENCY FINANCIAL REPORT

LICENSE FEES

HISTORY OF THE NRC

CAREER OPPORTUNITIES

NRC ETHICS

AGENCY STATUS

CONTACT US
        Popular Documents
INFO DIGEST

FACT SHEETS & BROCHURES

FORMS

ELECTRONIC SUBMITTALS APPLICATION

ADJUDICATORY SUBMISSIONS

NRC REPORTS - NUREG

NRC REGULATIONS - 10-CFR

INSPECTION REPORTS

PLAIN WRITING

ENFORCEMENT ACTIONS

RULEMAKING

GLOSSARY
        Stay Connected
    
    
    
    
    United States Nuclear Regulatory Commission
    
    
    
    
    Regulations.gov

USA.gov

FOIA

Whistleblower Protection

No Fear EEO

Inspector General

Site Map

Accessibility

Privacy Policy

Site Disclaimer

For Employees