A series of measurements were performed to determine the flow characteristics of the primary system and establish base points for use in future checks on primary system flow. The primary flow was determined for each pump operating individually as well as for various pump combinations. A flow coastdown test was performed to evaluate the primary flow decay following loss of pumping power. The results of these tests show that the total primary flow agrees closely with the predicted flow. The flow coastdown tests indicate that more flow than had been expected is available immediately after loss of all primary pumps therefore, the safety margin in heat transfer capacity during and shortly after the automatic reactor scram, which follows loss of primary pumps, is larger than had been predicted. /Author/

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number NSS-114.
  • Corporate Authors:

    New York Shipbuilding Corporation

    Savannah Nuclear Technology Department
    Camden, NJ  United States 
  • Authors:
    • Lemon, J E
  • Publication Date: 1962-5-23

Media Info

  • Features: Figures; References; Tables;
  • Pagination: 12 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026546
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Report/Paper Numbers: NSS-114
  • Contract Numbers: MA-1675
  • Files: TRIS, USDOT
  • Created Date: May 11 1973 12:00AM