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Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System

Oak Ridge National Laboratory

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Publications:

PDF Document Publication11-G00239_ID2603 (2).pdf (847 KB)


Technology Marketing Summary

Researchers at ORNL have developed an integrated system that reduces the total life-cycle cost of used fuel storage while improving overall safety. This multicanister approach provides superior assembly and burnup/damaged fuel capacity. The invention also reduces the need for future repackaging of fuel for transit or storage.

Description

The shutdown of the Yucca Mountain Project is leading to increased reliance on
dry cask storage of used nuclear fuel at existing plant sites. Because a long-term
plan for used fuel disposal does not yet exist, a variety of large capacity storage
and transportation casks will continue to be loaded at these sites. However, the
majority of these casks will not satisfy expected requirements for direct disposal
of used fuel at sites requiring low thermal profiles, so they will require repackaging
of the fuel for transportation and/or disposal. Repackaging fuel, particularly after
an extended storage period, leads to significant radiological, operational, and
financial liabilities.

 

Benefits

This invention reduces or eliminates the need for future repackaging by supporting
multiple used fuel disposal options, while increasing operational flexibility and
safety. The system’s unique features enable canisters to be handled separately or
collectively within the larger storage cask. In addition, the system offers potential
reductions in cask loading and drying time; a higher percentage of fuel to meet
subcriticality requirements; the incorporation of features for handling damaged
fuel assemblies after transport; achievement of geologic disposal thermal
management requirements; and, a reduction in overall radiation exposure and
fuel handling risk. All of these features also eliminate the need to upgrade current
structures or crane capacities at existing nuclear facilities.

•Allows improved decay heat management of high-burnup and mixed oxide fuel
•Enables increased percentage of fuel acceptable in terms of subcriticality requirements
•Works within existing framework and overpack designs
•Features lighter, easier-to-handle small modular canisters
•Features reusable large storage canister

Applications and Industries

•Allows improved decay heat management of high-burnup and mixed oxide fuel
•Enables increased percentage of fuel acceptable in terms of subcriticality requirements
•Works within existing framework and overpack designs
•Features lighter, easier-to-handle small modular canisters
•Features reusable large storage canister

More Information

John Scaglione and John Wagner. Flexible Integrated Modular Used Nuclear Fuel Storage, Transportation, and Disposal Canister System (FIRST), U.S. Provisional Patent Application US 61/509,715, filed July 20, 2011.

Patents and Patent Applications
ID Number
Title and Abstract
Primary Lab
Date
Application 20130077728
Application
20130077728
STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR FUEL ASSEMBLIES
An integrated storage, transportation and disposal system for used fuel assemblies is provided. The system includes a plurality of sealed canisters and a cask sized to receive the sealed canisters in side by side relationship. The plurality of sealed canisters include an internal basket structure to receive a plurality of used fuel assemblies. The internal basket structure includes a plurality of radiation-absorbing panels and a plurality of hemispherical ribs generally perpendicular to the canister sidewall. The sealed canisters are received within the cask for storage and transportation and are removed from the cask for disposal at a designated repository. The system of the present invention allows the handling of sealed canisters separately or collectively, while allowing storage and transportation of high burnup fuel and damaged fuel to the designated repository.
Oak Ridge National Laboratory 07/20/2012
Filed
Technology Status
Technology IDDevelopment StageAvailabilityPublishedLast Updated
UT-B ID 201102603ProposedAvailable11/21/201110/25/2011

Contact ORNL About This Technology

To: Eugene Cochran<cochraner@ornl.gov>