Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)

TRIGA Fuel Classification
Spent Nuclear Fuel
Transfer Data Form


PDF version available
DOWNLOAD full paper in PDF format.

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 Form


Presented by

Kraig M. Wendt

Lockheed Martin Idaho Technologies of the INEL

Appendix A, Section 1.1

Fuel Name and Type:
Fuel Producer:
Reactor Name:
Contact Name:

Appendix A, Section 1.2:
New Fuel Description

Physical Description

1. Fuel Dimensions and Shapes

2. Fuel Components

3. Fuel Configuration as Shipped

4. Fuel Weights

Appendix A, Section 1.2

Drawings and physical description of fuel rods

The following are preferences of acceptable drawings/descriptions of spent nuclear TRIGA fuels:

1. Fabrication schematics with tabularized physical data

2. Summation drawings (examples follow) with physical
data documented in margins

3. Tabularized physical data with written descriptions

Appendix A, Section 1.3:
Shipping Package Description

Description of Shipping Process

The information need not be provided if you are using any cask for which facility safety documentation exists at the INEL:

Appendix A, Section 1.3:
Shipping Package Description

If you are planning to use a different Spent Nuclear Fuel Cask, then two (2) copies of each of the following documentation must be provided:

1. Copy certificate of compliance or certificate of competent authority

2. Safety analysis report for packaging (SARP)

3. Poison, poison inserts, spacers and related certificates

4. Decontamination procedures and precautions

5. Load test certification of lifting/handling components

6. Detailed drawings of package showing at least the following information:

a. Dimensions
b. Weights
c. Surface finish (roughness, painting, coatings,...etc.)
d. Materials of construction
e. Other information pertinent to handling and unloading

7. Drawings of package handling devices showing the following information:

a. Type of load bar or lifting yoke
b. Lid removal tools, sizes and description of lid bolts
c. Special fuel removal tools, if any
d. Crane attachment details
e. Other information pertinent to handling and unloading

8. Descriptive photographs of the package

9. List of handling and loading/unloading equipment furnished

10. Diagrams involving lifting/handling configurations of the cask container including lifting points, boxes, spacers, tie downs

11. Loading/unloading and handling procedures

Appendix A, Section 2.1:
New Fuel, Fuel Materials Description

1. Fuel Type (Rod, Pellet, etc.)

2. Chemical form and fabrication (UZrHx, UO2, etc.)

3. Initial fissile material enrichment U-235, Pu-, Th, etc. material & weight, % enrichment

Material 1_________

Material 2 _________

4. Fuel additives (Alloys, organics, poisons, etc), weight

Material 1 _________ Weight________%________

Material 2 _________ Weight________%________

Provide weight basis per element

Appendix A. Section 2.2:
New fuel, Cladding Materials Description

1. Cladding Material (Zr, Al, Stainless Steel,...etc.)

2. Cladding thickness (mm):

Appendix A, Section 2.3:
Other Materials of Construction

Material 1 _________ Weight________or

Material 2 _________ Weight________or

Appendix A, Section 3.1:
Spent Fuel, Operation History

1. Unit identification (ID NO.)___________________________

2. Unit burnup (Cumulative Fission)__________________
Provide as megawatt-days/metric ton of fissile material

3. Operating or burn-up history of the fuel

4. Isotopic listing contributing top 95% of radiation

5. Date of last criticality:_________________________

Appendix A, Section 3.2:
Spent fuel, Operating History

Physical condition of the fuel elements:

1. Pictures/videos

2. Estimated cladding corrosion with water chemistry

Appendix A, Section 3.3:
Description of Canned/Recanned Fuel

If you are planning to use a can, or if the spent fuel is already canned, the information and documentation listed under items 1 through 6 of this section (Section 3.3) must be provided.

1. All canned fuel will be opened and repackaged

2. Can must be certified with SARP plus receipt and
shipping facility acceptable

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

Useful Links


ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department
9700 South Cass Ave., Argonne, IL 60439-4814
A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC

Last modified on July 29, 2008 11:33 +0200