Waste Management

Heavy water is used both for moderating nuclear fission and transporting heat in CANDU reactors. As a result of heavy water use in these systems, tritium is produced in small quantities from thermal neutron activation of deuterium. The presence of tritium in the heavy water contributes to the radiation dose of the reactor staff and radioactive emission from the reactor facility. Tritium dose is usually controlled through design and operating procedures that minimize leaks and limit exposure to the tritiated water. Many of the CANDU operators have also reduced the operational tritium concentration through detritiation of the heavy water from the reactor. Detritiation is carried out in a centralized facility, such as the Tritium Removal Facility in Darlington, which provides this service to Ontario’s nuclear reactor fleet. Detritiation reduces both tritium emission and dose to workers and the public from reactor operation.

The Nuclear Regulatory Commission is issuing a proposed interpretation of its low-­level radioactive waste disposal regulations that would permit licensees to dispose of waste by transfer to persons who hold specific disposal exemptions. The NRC said that it will consider approval of requests for specific exemptions only if they are for the disposal of very low-­level radioactive waste by land burial. Notice of the proposed interpretive rule was published in the March 6 Federal Register.

Visitors explore the exhibits and interactive displays at the K-25 History Center at Oak Ridge. Photo: DOE

The Department of Energy’s Oak Ridge Office of Environmental Management and its contractor URS/CH2M Oak Ridge hosted a ribbon-­cutting ceremony on February 27 for the new K-­25 History Center on the site of the former uranium enrichment plant. Located next to the original foundation for the K-­25 building, the center was built to honor and preserve the stories of the workers who constructed and operated the K-­25 complex during World War II and the Cold War.

Speaking before the House Appropriations Committee’s Subcommittee on Energy and Water Development on March 3, Rita Baranwal, the Department of Energy’s assistant secretary for nuclear energy, said that the DOE has prepared a request for proposal for an interim storage site for radioactive waste. “The intent is for the basic design of an interim storage facility,” she said.

Following a comprehensive and open national consultation, the United Kingdom’s Radioactive Waste Management (RWM) organization on February 18 published its approach to evaluating possible sites in England and Wales for a deep geological disposal facility. A wholly owned subsidiary of the U.K. government’s Nuclear Decommissioning Authority, RWM will be responsible for the siting, construction, operation, and eventual closure of a disposal facility for the United Kingdom’s high-­ and intermediate-­level radioactive waste.

International Atomic Energy Agency member states operating or having previously operated a research reactor are responsible for the safe and sustainable management of associated radioactive waste, including research reactor spent nuclear fuel (RRSNF). Management includes storage and ultimate disposal of RRSNF, or the corresponding equivalent waste generated and returned following reprocessing of the spent fuel. Currently, there are 259 research reactors operating, planned, or under construction around the world [1]. An additional 147 research reactors are in extended or permanent shutdown, or under decommissioning.

One key challenge to developing general recommendations for RRSNF management options lies in the diversity of spent fuel types, locations, and national or regional circumstances, rather than mass or volume alone, particularly since typical RRSNF inventories are relatively small. Currently, many countries lack an effective long-term strategy for managing RRSNF. Many research reactor organizations know they have responsibility for the spent fuel, however, they do not know how to decide among multiple options for its management. A methodical review and compilation of technology options for RRSNF management is needed.

The gel is applied to an area (left), where it is allowed to work for two to three hours before being removed. The final activity of the cleaned area (right) was counted using HPGe and Ludlum alpha/beta radiation detectors. Photos courtesy of ANL.

Current techniques for radiological decontamination often involve debasing or demolishing structures to contain contaminated dust and haul debris away. This is a costly method of decontaminating buildings and structures. If, however, effective nondestructive methods can be found, significant savings are possible. One such method, based on new research from engineers at the Department of Energy’s Argonne National Laboratory in Lemont, Ill., is now available.