CONTAINMENT PRESSURE ANALYSIS REPORT

This report presents an analysis made to determine the maximum pressure existing in the containment vessel of the USAEC Nuclear Merchant Ship Savannah after a maximum credible incident. The maximum credible incident considered is a primary rupture that causes release and expansion of the total primary system water and the secondary steam-water mixture from one steam generator. The analysis considers both the rate of leakage through the primary system rupture and the rate of heat absorption from the flashed mixture by the colder, uninsulated surroundings. The results of this analysis show that the containment pressure rises for approximately 24 sec after an incident and then decreases. The maximum pressure is 173 psig.

• Supplemental Notes:
  • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BAW-1123.
• Corporate Authors:

  Babcock and Wilcox Company

  Atomic Energy Division
  Lynchburg, VA  United States  24504
• Authors:
  • Lemon, J E
  • Ellington, J C
• Publication Date: 1958-10-10

Media Info

• Pagination: 11 p.

Subject/Index Terms

• TRT Terms: Design; Nuclear power plants; Nuclear reactors; Safety
• Old TRIS Terms: Nuclear reactor design; Nuclear reactor safety
• Subject Areas: Design; Marine Transportation; Safety and Human Factors; Vehicles and Equipment;

Filing Info

• Accession Number: 00026070
• Record Type: Publication
• Source Agency: Maritime Administration
• Contract Numbers: AT(30-4)-274
• Files: TRIS, USDOT
• Created Date: Mar 2 1974 12:00AM