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 Resulting from International AgreementsExperimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions (NUREG/IA-0211)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0211 (PDF - 33.74 MB)Publication Information **Date Published:** March 2005 **Prepared by:** L. Yegorova, K. Lioutov, N. Jouravkova, A. Konobeev Nuclear Safety Institute of Russian Research Centre "Kurchatov Institute" Kurchatov Square 1, Moscow 123182, Russian Federation V. Smirnov, V. Chesanov, A. Goryachev State Research Centre "Research Institute of Atomic Reactors" Dimitrovgrad 433510, Russian Federation Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 **Prepared for:** U.S. Nuclear Regulatory Commission (United States), Institute for Radiological Protection and Nuclear Safety (France), and Joint Stock Company "TVEL" (Russian Federation) Availability Notice Abstract During 2001-2004, research was performed to develop test data on the embrittlement of niobium-bearing (Zr-1%Nb) cladding of the VVER type under loss-of-coolant accident (LOCA) conditions. Procedures were developed and validated to determine the zero ductility threshold. Pre-test and post-test examinations included weight gain and hydrogen content measurements, preparation of metallographic samples, and examination of samples using optical microscopy, scanning electron microscopy and transmission electron microscopy. Sensitivity of the zero ductility threshold to heating and cooling rates was determined. Oxidation kinetics and ductility threshold were measured for the standard E110 alloy, six variants with different impurities, Zircaloy, and irradiated E110. Oxidation temperatures were varied from 800-1200 C, and mechanical (ring compression) testing temperatures were varied from 20-300 C. It was concluded that (a) the current type of E110 cladding has an optimal microstructure, (b) oxidation and ductility of the oxidized cladding are very sensitive to microchemical composition and surface finish, (c) the use of sponge zirconium for fabrication of cladding tubes provides a significant reduction of the oxidation rate and an increase in the zero ductility threshold, and (d) additional improvement in oxidation and ductility can be achieved by polishing the cladding surface. 
      
      Page Last Reviewed/Updated Tuesday, March 09, 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