You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass

    International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels

    Published: 01 January 2010

      Format Pages Price  
    PDF (1.1M) 25 $25   ADD TO CART
    Complete Source PDF (19M) 286 $89   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    The International Atomic Energy Agency (IAEA) has conducted a series of coordinated research projects (CRPs) that have focused on irradiated reactor pressure vessel (RPV) steel fracture toughness properties and approaches for assuring structural integrity of RPVs throughout operating life. A series of nine CRPs has been sponsored by the IAEA, starting in the early 1970s, focused on neutron radiation effects on RPV steels. The purpose of the CRPs was to develop comparisons and correlations to test the uniformity of irradiated results through coordinated international research studies and data sharing. Consideration of dose rate effects, effects of alloying (nickel, manganese, silicon, etc.) and residual elements (e.g., copper and phosphorus), and drop in upper shelf toughness is also important for assessing neutron embrittlement effects. The ultimate use of embrittlement understanding is assuring structural integrity of the RPV under current and future operation and accident conditions. Material fracture toughness is the key ingredient needed for this assessment, and many of the CRPs have focused on measurement and application of irradiated fracture toughness. This paper presents an overview of the progress made since the inception of the CRPs in the early 1970s. The chronology and importance of each CRP have been reviewed and put into context for continued and long-term safe operation of RPVs.


    reactor pressure vessels, fracture toughness, master curve, radiation embrittlement, Charpy impact, nickel, copper, PWR, WWER

    Author Information:

    Server, William L.
    ATI Consulting, Pinehurst, NC

    Nanstad, Randy K.
    Oak Ridge National Laboratory, Oak Ridge, TN

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP49000S