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

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

CASK SELECTION


PDF version available
DOWNLOAD full paper in PDF format.


Contact:
Mr. Keith Brown
Science Applications International Corp.
20201 Century Blvd., Third Floor
Germantown, MD 20874
Tel.: +1-301-353-8343
Fax: +1-301-428-1973
E-mail: Keith_Brown@ccmail.gmt.saic.com

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


L.4.1

CASK SELECTION

by

Keith Brown

Science Applications International Corporation

Cask Selection Considerations
  • Compatibility with Fuel Assemblies
  • Compatibility with Facility
  • Availability of Cask
  • Personal Preference

Compatibility with Fuel Assemblies
  • Physical Dimensions, i.e., Will Assemblies Fit in the Basket?

  • Fissile Content - Grams of U235, Grams of U, Enrichment

  • Cool Down Time Requirements

  • Decay heat Load

  • Activity and Does Rates

Compatibility with Facility
  • Crane Capacity

  • Maximum and Minimum Crane Hook Height

  • Allowable Floor Loading and Spent Fuel Pool Depth

  • Physical Size of Doorways

  • Clearances For Handing The Cask in the Building, Spent Fuel Storage Pool, and/or Hot Cell

Current Cask Inventory

Cask


Owner

Available to Ship MTR

Available to Ship TRIGA

Number
Available

TN7/2

NCS

Currently

No

2

GNS-11

NCS

Currently

No

2

IU-04

TN

Currently

Limited

5

LHRL 120

ANSTO

Certifiable

No

1

TN 6-1, 6-3

NCS

Certifiable

Pending

1 Each

GE 2000

GE

Currently

Pending

2

NAC-LWT

NAC

Currently

Pending

5

Transfer System

NAC

Currently

Pending

1


Future Casks Planned

Cask

Owner
Available to
Ship MTR
Available to Ship TRIGA Number Available

GNS (New)

NCS

1997

1997

2

TN (New)

TN

1998

1998

2

NL-1/2

NAC

NRU, NRX Only

No

5

Transfer System

NCS

1997

1997

1


GNS-11
Aluminum MTR Elements LEU HEU
Maximum Number of Elements 33 33
Maximum Enrichment 20% 94%
Maximum U 1635 g 335 g
Maximum U235 323 g 268 g
Maximum Decay heat Load 48.5 W 48.5 W
Minimum Cooldown Time 360 Days 1808 Days
Maximum Activity 1 Pbq 1 Pbq

TRIGA

Not Currently Certified for TRIGA Fuel


TN 7/2
Aluminum MTR Elements
Maximum Number of Elements 64
Maximum Enrichment 80-93
Maximum U 363 g
Maximum U235 290 g
Maximum Decay Heat Load 125 W
Minimum Cooling Time 170 Days
Maximum Activity 740 Tbq

TRIGA

Not Currently Certified for TRIGA Fuel


NAC-LWT
Aluminum MTR Elements HEU LEU
Maximum Number of Elements 42 (Cropped)
28 (Uncropped)
42 (Cropped)
28 (Uncropped)
Maximum Enrichment 80-94% 20%
Maximum U 377 g 1722 g
Maximum Decay Heat Load 30 w/Element 24 w/Element
Minimum Cooling Time 3 Years 1 Year
Maximum Ave. Burnup 550,000 MWD/MTU 90,490 MDW/MTU

TRIGA

Not Currently Certified for TRIGA Fuel - Certification is
Planned During 1997


IU-04
 Aluminum MTR Elements  
 Maximum Number of Elements  36 in Basket TN 9083
40 in Basket AA 267
 Maximum Enrichment  100%
 Maximum U235 Concentration  0.73 g/cm
 Maximum Decay Heat Load  <132 w/Element (TN 9083)
<80 w/Element (AA 267)
 Minimal Fuel Core Thickness  0.5 mm
 Minimal Cladding Thickness  0.2 mm

IU-04 (Cont'd)
TRIGA
Maximum Number of Elements Any number that can be plaed in basket TN 9083, tight or not (144?)
Cladding Aluminum
Composition
Uranium 8%
Zirconium Hydride 92%
Maximal Contents
Uranium Weight <199 g/Element
Uranium Enrichment 20%

GE 2000
Aluminum MTR Elements HEU LEU
Maximum Number of Elements

42 (Chopped)

21 (UnChopped)

42 (Chopped)

21 (Unchopped)

Maximum Enrichment 93.2% 20%
Maximum U235 355 g 355 g
Maximum Burnup 533 GWD/MTU 100 GWD/MTU
Maximum Decay Heat Load 35 W 35 W
Maximum Cooling Time 880 Days 880 Days


TRIGA

Not Currently Certified for TRIGA Fuel - Application has been Submitted for Certification of up to 84 TRIGA Elements, Enriched Between 20% and 93%, with Aluminum, Inconel, or Stainless Steel Cladding










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

DOCUMENTS


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 11:34 +0200