Utilities worldwide are using dry-cask storage systems to handle the ever-increasing number of discharged fuel assemblies from nuclear power plants. In the United States and possibly elsewhere, this trend will continue until an acceptable disposal path is established. The recent Fukushima nuclear power plant accident, specifically the events with the storage pools, may accelerate the drive to relocate more of the used fuel assemblies from pools into dry casks. Many of the newer cask systems incorporate dual-purpose (storage and transport) or multiple-purpose (storage, transport, and disposal) canister technologies. With the prospect looming for very long term storage — possibly over multiple decades — and deferred transport, condition- and performance-based aging management of cask structures and components is now a necessity that requires immediate attention. From the standpoint of consequences, one of the greatest concerns is the rupture of a substantial number of fuel rods that would affect fuel retrievability. Used fuel cladding may become susceptible to rupture due to radial-hydride-induced embrittlement caused by water-side corrosion during the reactor operation and subsequent drying/transfer process, through early stage of storage in a dry cask, especially for high burnup fuels. Radio frequency identification (RFID) is an automated data capture and remote-sensing technology ideally suited for monitoring sensitive assets on a long-term, continuous basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy’s Packaging Certification Program for tracking and monitoring drums containing sensitive nuclear and radioactive materials. The ARG-US RFID system is versatile and can be readily adapted for dry-cask monitoring applications. The current built-in sensor suite consists of seal, temperature, humidity, shock, and radiation sensors. With the universal asynchronous receiver/transmitter interface in the tag, other sensors can be easily added as needed. The system can promptly generate alarms when any of the sensor thresholds are violated. For performance and compliance records, the ARGUS RFID tags incorporate nonvolatile memories for storing sensory data and history events. Over the very long term, to affirmatively monitor the condition of the cask interior (particularly the integrity of cover gas and fuel-rod cladding), development of enabling technologies for such monitoring would be required. These new technologies may include radiation-hardened sensors, in-canister energy harvesting, and wireless means of transmitting the sensor data out of the canister/cask.
Skip Nav Destination
ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management
September 25–29, 2011
Reims, France
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
978-0-7918-5498-3
PROCEEDINGS PAPER
Advanced Surveillance Technologies for Used Fuel Long-Term Storage and Transportation Available to Purchase
Hanchung Tsai,
Hanchung Tsai
Argonne National Laboratory, Argonne, IL
Search for other works by this author on:
Yung Y. Liu,
Yung Y. Liu
Argonne National Laboratory, Argonne, IL
Search for other works by this author on:
Mark Nutt,
Mark Nutt
Argonne National Laboratory, Argonne, IL
Search for other works by this author on:
James Shuler
James Shuler
U.S. Department of Energy, Washington, DC
Search for other works by this author on:
Hanchung Tsai
Argonne National Laboratory, Argonne, IL
Yung Y. Liu
Argonne National Laboratory, Argonne, IL
Mark Nutt
Argonne National Laboratory, Argonne, IL
James Shuler
U.S. Department of Energy, Washington, DC
Paper No:
ICEM2011-59032, pp. 699-706; 8 pages
Published Online:
August 17, 2012
Citation
Tsai, H, Liu, YY, Nutt, M, & Shuler, J. "Advanced Surveillance Technologies for Used Fuel Long-Term Storage and Transportation." Proceedings of the ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Reims, France. September 25–29, 2011. pp. 699-706. ASME. https://doi.org/10.1115/ICEM2011-59032
Download citation file:
37
Views
Related Proceedings Papers
Related Articles
Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan
J. Eng. Gas Turbines Power (October,2010)
Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards
ASME J of Nuclear Rad Sci (April,2020)
Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
J. Eng. Gas Turbines Power (October,2010)
Related Chapters
Utilities’ Perspective of Spent Fuel Storage
Global Applications of the ASME Boiler & Pressure Vessel Code
Development and Structure of the German Common Cause Failure Data Pool (PSAM-0020)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Off-Site Fabrication and Assembly
Consensus on Pre-Commissioning Stages for Cogeneration and Combined Cycle Power Plants