Transient performance of the N.S. Savannah reactor plant was analyzed by analog computer. Analysis included the control and safety system actions required to prevent plant damage following operating and accident transients, and the possible simplification of the safety system. Accidents of greater severity, automatic limiting advices to preclude safety action, and realistic parameters based on operating experience were considered. The automatic limiting action (corrective action of less severity and reliability than a scram) stopped undesirable rod withdrawal or inserted rods at normal control speeds. Combined with safety action, forming the graded protective system, it also stopped scram at high speed which automatically limited excursions from normal operating conditions. Comparison between computer results and actual Savannah testing indicated analog simulation is reliable for transient studies. Present rod rates available to the controller were found adequate and safe, and installation of the graded protective system did not appear justified.

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BAW-1260.
  • Corporate Authors:

    Babcock and Wilcox Company

    Atomic Energy Division
    Lynchburg, VA  United States  24504
  • Authors:
    • Rosser, R M
  • Publication Date: 1962-11

Media Info

  • Features: Appendices; Figures; References; Tables;
  • Pagination: 197 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026547
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Report/Paper Numbers: BAW-1260
  • Contract Numbers: AT(30-1)-2721
  • Files: TRIS, USDOT
  • Created Date: May 11 1973 12:00AM