The Department of Energy mandated the termination of the Integral Fast Reactor (IFR) Program, effective October 1, 1994. To comply with this decision, Argonne National Laboratory-West (ANL-W) prepared a plan providing detailed requirements to maintain the Experimental Breeder Reactor-II (EBR-II) in a radiologically and industrially safe condition, including removal of all irradiated fuel assemblies from the reactor plant, and removal and stabilization of the primary and secondary sodium, a liquid metal used to transfer heat within the reactor plant. The EBR-II is a pool-type reactor. The primary system contained approximately 325 m3 (86,000 gallons) of sodium and the secondary system contained 50 m3 (13,000 gallons). In order to properly dispose of the sodium in compliance with the Resource Conservation and Recovery Act (RCRA), a facility was built to react the sodium to a solid sodium hydroxide monolith for burial as a low level waste in a land disposal facility. Deactivation of a liquid metal fast breeder reactor (LMFBR) presents unique concerns. Residual amounts of sodium remaining in circuits and components must be passivated, inerted, or removed to preclude future concerns with sodium-air reactions that could generate potentially explosive mixtures of hydrogen and leave corrosive compounds. The passivation process being implemented utilizes a moist carbon dioxide gas that generates a passive layer of sodium carbonate/sodium bicarbonate over any quantities of residual sodium. Tests being conducted will determine the maximum depths of sodium that can be reacted using this method, defining the amount that must be dealt with later to achieve RCRA clean closure. Deactivation of the EBR-II complex is on schedule for a March, 2002, completion. Each system associated with EBR-II has an associated layup plan defining the system end state, as well as instructions for achieving the layup condition. A goal of system-by-system layup is to minimize surveillance and maintenance requirements during the interim period between deactivation and decommissioning. The plans also establish document archival of not only all the closure documents, but also the key plant documents (P&IDs, design bases, characterization data, etc.) in a convenient location to assure the appropriate knowledge base is available for decommissioning, which could occur decades in the future.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3595-2
PROCEEDINGS PAPER
Shutdown and Closure of the Experimental Breeder Reactor–II
John A. Michelbacher,
John A. Michelbacher
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Carl E. Baily,
Carl E. Baily
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Daniel K. Baird,
Daniel K. Baird
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
S. Paul Henslee,
S. Paul Henslee
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Collin J. Knight,
Collin J. Knight
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Kenneth E. Rosenberg
Kenneth E. Rosenberg
Argonne National Laboratory, Idaho Falls, ID
Search for other works by this author on:
John A. Michelbacher
Argonne National Laboratory, Idaho Falls, ID
Carl E. Baily
Argonne National Laboratory, Idaho Falls, ID
Daniel K. Baird
Argonne National Laboratory, Idaho Falls, ID
S. Paul Henslee
Argonne National Laboratory, Idaho Falls, ID
Collin J. Knight
Argonne National Laboratory, Idaho Falls, ID
Kenneth E. Rosenberg
Argonne National Laboratory, Idaho Falls, ID
Paper No:
ICONE10-22462, pp. 857-865; 9 pages
Published Online:
March 4, 2009
Citation
Michelbacher, JA, Baily, CE, Baird, DK, Henslee, SP, Knight, CJ, & Rosenberg, KE. "Shutdown and Closure of the Experimental Breeder Reactor–II." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 14–18, 2002. pp. 857-865. ASME. https://doi.org/10.1115/ICONE10-22462
Download citation file:
5
Views
0
Citations
Related Proceedings Papers
Related Articles
Experimental Determination of Sodium Superheat Employing LMFBR Simulation Parameters
J. Heat Transfer (August,1974)
Behavior of Inert Gas Bubbles in Forced Convective Liquid Metal Circuits
J. Heat Transfer (February,1976)
Adaptive Collocation Method for Simultaneous Heat and Mass Diffusion With Phase Change
J. Heat Transfer (August,1984)
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Internal Requirements of the DOE
Decommissioning Handbook
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential