PARAMETRIC STUDY OF RADIATION DOSE RATES FROM RAIL AND TRUCK SPENT FUEL TRANSPORT CASKS

Neutron and gamma dose rates from typical rail and truck spent fuel transport casks are reported for a variety of spent PWR fuel sources and cask conditions. The IF 300 rail cask and NLI 1/2 truck cask were selected for use as approprite cask models. All calculations (cross section preparation, generation of spent fuel source terms, radiation transport calculations, and dose evaluation) were performed using various modules of the SCALE computational system. Conditions or parameters for which there were variations between cases include detector distance from cask, spent fuel cooling time, the setting of fuel or neutron shielding cavities to either wet or dry, the cobalt content of assembly materals, normal fuel assemblies and consolidated cannisters, the geometry mesh interval size, and the order of the angular quadrature set.

• Corporate Authors:

  Oak Ridge National Laboratory

  P. O. Box 2008
  Oak Ridge, TN  United States  37831
• Authors:
  • Parks, C V
  • Hermann, O W
  • Knight, J R
• Publication Date: 1985-8

Media Info

• Features: Figures; References; Tables;
• Pagination: 36 p.

Subject/Index Terms

• TRT Terms: Containers; Electromagnetic radiation; Freight transportation; Hazardous materials; Measurement; Nuclear gages
• Subject Areas: Freight Transportation; Highways; Safety and Human Factors; I81: Accident Statistics;

Filing Info

• Accession Number: 00457123
• Record Type: Publication
• Source Agency: National Technical Information Service
• Report/Paper Numbers: ORNL/CSD/TM-227
• Files: TRIS
• Created Date: Aug 27 2004 9:39PM