IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
TRIGA Fuel Classification
Spent Nuclear Fuel
Transfer Data
PDF version
NOT available
This information was provided in a working group
session and is not available electronically. Please contact Mr. Kraig Wendt at
the address listed below to request a copy of this document. The information
included is listed below.
Contact:
Mr. Kraig M. Wendt
Lockheed Martin Idaho Technologies
P.O. Box 1625
Idaho Falls, ID 83415-5306
Tel.: +1-208-526-3860
Fax: +1-208-526-7112
E-mail: [email protected]
IAEA/USA Interregional Training Course
Technical and Administrative Preparations Required for Shipment of Research Reactor Spent
Fuel to its Country of Origin
13-24 January 1997
Argonne, IL
Lecture L.3.2
TRIGA Fuel Classification
Spent Nuclear Fuel
Transfer Data
APPENDIX A
Presented by
Kraig M. Wendt
Lockheed Martin Idaho Technologies of the INEL
- Appendix A Spent Nuclear Fuel Transfer Data :
Contains sample Appendix A data for spent fuel from the University of Illinois TRIGA reactor.
- Isotopic Analysis (H-3 to
Yb-172 and Actinides)
- Fuel Assembly Specific Data
- Fuel Element Number
- BOL Mass of U and U-235
- Mass of U, U-235, U-236, U-233
- Inventory Decayed to July 1, 2030
- Mass of U, U-235, U-236, U-233
- Mass of Pu, Pu-239, Pu-240, Pu-241
- Time in Reactor (days)
- Power Level (Kilowatts)
- Cooling Time (days)
- Percent U-235 burnup
- Decay Heat (Watts)
- Basis Burnup Data per Element
- A sample NUCLEAR MATERIAL TRANSACTION REPORT of
the U.S. Department of Energy and the Nuclear Regulatory Commission
- Curves showing Decay Heat as a Function of Time and
Burnup
- Curves showing TRIGA fuel element 3.0 ft. dose rate
at midplane
- Isotopic Data for Aluminum-clad TRIGA fuel, Stainless-steel clad TRIGA fuel, and FLIP TRIGA fuel
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