GAS-COOLED REACTOR FOR SHIP PROPULSION. PART 2

Reports on the feasibility of zirconium hydride as the moderator material for a gas-cooled reactor for ship propulsion are presented. Discusses U02 as the fuel to be present in the reactor dispersed in stainless steel and clad with the same material.

• Supplemental Notes:
  • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number GA-87-Pt-2.
• Corporate Authors:

  General Dynamics

  Quincy, MA  United States  02169
• Authors:
  • Sharp, R
• Publication Date: 1957-4-8

Subject/Index Terms

• TRT Terms: Design; Materials selection; Nuclear fuels; Nuclear reactor coolants; Nuclear reactors
• Old TRIS Terms: Materials evaluation; Nuclear reactor design
• Subject Areas: Design; Energy; Marine Transportation; Vehicles and Equipment;

Filing Info

• Accession Number: 00027540
• Record Type: Publication
• Source Agency: Maritime Administration
• Report/Paper Numbers: GA-87-Pt-2 Feas Rpt
• Contract Numbers: AT(04-3)-118
• Files: TRIS, USDOT
• Created Date: Jul 9 1973 12:00AM