Finalization of the NMSR shield design in accord with the final core design required a recalculation of the activity levels in the primary coolant. This source is, in general, the dominant factor in sizing the containment gamma shield and effects the neutron shield in limited areas. The specific volumetric gamma source strengths previously reported are significantly revised downward as justified in this report. The activity source reactions and the general formula for calculating the source strengths are reviewed. Subsequent sections deal with the key parameters, fast neutron fluxes and activation cross sections, and report the results. Comparison of the revised methods of calculation with the old is incorporated as required.

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BAW-1126.
  • Corporate Authors:

    Babcock and Wilcox Company

    Atomic Energy Division
    Lynchburg, VA  United States  24504
  • Authors:
    • Turner, M A
  • Publication Date: 1958-12

Media Info

  • Features: References;
  • Pagination: 11 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026081
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Contract Numbers: AT(30-3)-274
  • Files: TRIS, USDOT
  • Created Date: Feb 14 1973 12:00AM