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

    Theoretical Analysis of Sodium Removal from Fast Flux Test Facility Fuel Subassemblies

    Published: 01 January 1937

      Format Pages Price  
    PDF (180K) 10 $25   ADD TO CART
    Complete Source PDF (4.3M) 238 $74   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 Fast Flux Test Facility (FFTF) is a 400 MWt, sodium cooled, nuclear fuels and materials test reactor being developed at the USAEC's Hanford Engineering Development Laboratory. The reactor fuel is clad with Type 316 stainless steel. In order to examine fuel, the sodium coolant must be removed in a manner which will not degrade the fuel cladding. Several possible processes are reviewed and a moderately detailed sizing analysis is given for the chosen process which is argon-moist argon-water rinsing.


    cleaning, stainless steels, sodium, subassemblies

    Author Information:

    Borisch, R. R.
    Development engineer, Westinghouse Hanford Company, Richland, Wash.

    Committee/Subcommittee: A01.06

    DOI: 10.1520/STP41384S