Radwaste Solutions

A rendering of Phase 1 of ISP’s proposed consolidated interim storage facility in Andrews County, Texas. Image: WCS

The Nuclear Regulatory Commission has released a draft environmental impact statement (EIS) for Interim Storage Partners’ (ISP) proposed consolidated interim storage facility (CISF) for spent nuclear fuel and greater-than-Class C (GTCC) waste in West Texas. Based on its environmental review of the CISF, the NRC staff issued a preliminary recommendation that an NRC license be granted to ISP to construct and operate the CISF to temporarily store up to 5,000 metric tons of uranium (MTU) in commercial spent fuel and GTCC waste for a licensing period of 40 years.

Deep in the underground of a New Mexico desert, the Department of Energy is studying the effects of high-level, heat-generating radioactive waste on water migration in the salt formations. At the Waste Isolation Pilot Plant (WIPP) near Carlsbad, N.M., a collaboration between Sandia, Los Alamos, and Lawrence Berkeley National Laboratories is performing a series of borehole-scale process tests, called the Brine Availability Test in Salt (BATS) project.

The National Nuclear Security Administration’s early-stage plan to dilute and dispose of 34 metric tons of surplus plutonium in the Waste Isolation Pilot Plant (WIPP) is technically viable, according to an April 30 release from the National Academies of Sciences, Engineering, and Medicine.

The Nuclear Regulatory Commission has rejected a number of contentions filed against Holtec International’s application to build and operate a consolidated interim storage facility (CISF) for spent nuclear fuel in southeastern New Mexico. On April 23, the commissioners voted to dismiss five separate appeals of the presiding Atomic Safety and Licensing Board’s decision to deny requests to intervene in the proceeding for Holtec’s license application.

Decommissioning work in parts of the Fukushima Daiichi plant in Japan has been delayed after engineers discovered that sandbags placed in the basements of buildings near Units 1 and 3 were found to contain excessive radiation levels. Tokyo Electric Power Company (TEPCO) operates the plant and is in charge of the decommissioning efforts following the accident caused by the earthquake and tsunami on March 11, 2011.

Recognizing the impacts of the current COVID–19 pandemic, the Nuclear Regulatory Commission has decided to extend the public comment period on a proposed interpretation of its low-level radioactive waste disposal regulations. The new deadline for comments is July 20. The proposed LLW interpretive rule, announced on March 6, would permit licensees to dispose of waste by transfer to persons who hold specific exemptions for the purpose of disposal (NN, Apr. 2020, p. 47).

An International Atomic Energy Agency team of experts said in a review published on April 2 that the two options for the controlled disposal of treated water stored at the Fukushima Daiichi nuclear power plant are “technically feasible.” A Japanese advisory subcommittee outlined the two options—vapor release and discharge to the sea—for the water that is being stored at the plant following the 2011 accident.

The NRC approved the transfer of the reactor's license to ADP CR3 for decommissioning.

The Nuclear Regulatory Commission approved the license transfer for the Crystal River-3 nuclear power plant from Duke Energy Florida to ADP CR3, enabling active decommissioning of the shuttered nuclear power plant, the agency announced on April 1.

Large-scale testing is done on the Spinionic rotating bed reactor system.

We live in a world where we are continually driven to increase efficiency while decreasing costs—to do more with less. The nuclear industry is no different. Developing innovative techniques or adapting creative ideas found in other industries can support that pursuit to reduce cost and, in this case, volumes of waste, while providing program certainty. Such actions build confidence in our industry and allow nuclear power to continue to be part of the narrative of our clean-energy future.

As nuclear power plants age and retire from service, many countries face significant challenges concerning the safe long-term storage and disposal of large volumes of low- and intermediate-level radioactive wastes (L&ILW). In Canada, Ontario Power Generation (OPG) is currently in the process of obtaining regulatory approval for a deep geological repository (L&ILW DGR) for such wastes from decommissioning and refurbishment of its heavy water reactors. OPG is exploring innovative methods and technologies to improve safety and reduce the processing, transportation, and disposal costs of these wastes. The volumes of metallic waste are of particular concern, because when metal corrodes it produces hydrogen that could lead to pressure buildup in the L&ILW DGR.

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.

A large-scale campaign to move spent nuclear fuel and high-level radioactive waste in the United States to a central repository or interim storage site does not appear to be coming anytime soon. External pressures, however, including a growing number of nuclear power plant closures and increased stakeholder demand to remove stranded spent fuel and HLW, are shifting focus to building the infrastructure needed to move large volumes of waste. This includes the design and manufacture of shielded transportation casks for shipping the waste by truck or rail.

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.

Participants to the 2017 Nuclear Criticality Safety Division topical meeting attended a tour of the WIPP facility, which marked its 20th anniversary this past year. Photos courtesy of WIPP

March 26, 2019, marked the 20th anniversary of the first shipment of transuranic (TRU) waste to the Waste -Isolation Pilot Plant (WIPP) facility in southeastern New Mexico. Celebrations of the 20-year mark of waste operations recognized the role of the WIPP facility in cleaning up legacy TRU waste from 22 generator sites nationwide.

The U.S. Nuclear Waste Technical Review Board (NWTRB or Board) recently completed an evaluation of Department of Energy activities related to transporting spent nuclear fuel (SNF) and high-level radioactive waste. These topics have been the subject of several Board meetings and associated reports, and in September 2019, the Board issued a report, Preparing for Nuclear Waste Transportation–Technical Issues That Need to Be Addressed in Preparing for a Nationwide Effort to Transport Spent Nuclear Fuel and High-Level Radioactive Waste [1], which focuses on the issues DOE will need to address to plan and implement an integrated transportation program. In its report, the Board describes 30 broad technical issues that DOE needs to address and offers three sets of findings and recommendations.