GA-4/GA-9 LEGAL WEIGHT TRUCK FROM REACTOR SPENT FUEL SHIPPING CASKS. PRELIMINARY DESIGN REPORT

The preliminary design report presents the results of General Atomics (GA) preliminary design effort to develop legal weight truck from reactor spent fuel shipping casks. The thermal evaluation of the Office of Civilian Radioactive Waste Management (OCRWM) cask considered normal and hypothetical accident conditions of transport. We employed analytical modeling as well as fire testing of the neutron shielding material to perform the evaluation. This document addresses the thermal design features of the cask, discusses thermal criteria, and summarizes the results of the thermal evaluationn, as well as results of structural containment and nuclear evaluations that support the design. Also included are the results of trade-off studies.

• Supplemental Notes:
  • Portions of this document are illegible in microfiche products.
• Corporate Authors:

  General Atomic Company

  10955 John Jay Hopkins Drive
  San Diego, CA  United States  92121
• Publication Date: 1990-4

Media Info

• Features: Figures; References; Tables;
• Pagination: 675 p.

Subject/Index Terms

• TRT Terms: Containers; Design; Honeycomb structures; Neutrons; Nuclear energy; Nuclear fuels; Nuclear reactors; Radioactive waste disposal; Spent reactor fuels; Structural analysis; Thermal analysis; Tractor trailer combinations; Trailers; Transportation safety; Trucks; Trucks by weight; Weight
• Uncontrolled Terms: Design criteria
• Old TRIS Terms: Neutron sources
• Subject Areas: Design; Energy; Highways; Motor Carriers; Safety and Human Factors; I82: Accidents and Transport Infrastructure;

Filing Info

• Accession Number: 00601080
• Record Type: Publication
• Source Agency: National Technical Information Service
• Report/Paper Numbers: DOE/ID/12698-1-Vol.2, GA-A-19862-Vol.2
• Files: TRIS
• Created Date: Jan 31 1991 12:00AM