In the early years of the Nuclear News capacity factors survey, any factor over 70 was deemed excellent; any factor under 50 was considered poor. By that standard, all but two operating U.S. power reactors chalked up excellent performance during 2017–2019. A record 809.4 TWh of electricity was generated in the United States from nuclear energy in 2019, according to the U.S. Energy Information Administration (EIA), besting the record of 807.1 TWh set in 2018.

Nuclear News staff developed the capacity factors survey in the early 1980s as a way to identify the most productive reactors in an expanding fleet. Fleet improvement was the industry’s self-identified goal, but no one could anticipate the startlingly rapid pace of improvement, spurred by the Institute of Nuclear Power Operations (INPO), which boosted fleetwide performance to highs that continue today.

The Optimus-H transport cask on display at the 2020 Waste Management Conference in Phoenix, Ariz.

Jeff England, director of transportation projects for NAC International, pointed to the large stainless steel canister, which looked like a giant-­sized silver dumbbell, perched on the flatbed of a semitrailer truck parked in the middle of the expansive exhibit hall in the Phoenix Convention Center. NAC, a provider of nuclear storage, transportation, and consulting services, was using the 2020 Waste Management Conference, held March 8–12 in Phoenix, Ariz., to unveil its newest transport casks, the Optimus-­H and Optimus-­L.

“These are a different niche,” England said of the casks, which were designed to transport radioactive materials, including remote-­handled transuranic waste, high-­activity intermediate-­level waste, low-­enriched uranium, and fissile materials. “You have a lot of [small] drum-­sized packages, and you also have a lot of big packages that will hold around 10 55-­gallon drums. But there’s not anything in between. We hold a 110-­gallon drum capacity.”

As the nuclear industry pursues a new generation of reactors to meet economic and political realities, the process for developing and qualifying new fuels and materials has come into focus. It’s clear that the 30-year development process the industry has come to expect is no longer viable, just as the economic reality of the current reactor fleet is increasingly coming under pressure from low-cost alternatives, particularly natural gas. To reduce carbon emissions while meeting ever-growing energy needs, new nuclear plants must be built soon.

The TCR program is leveraging an agile approach—one that is centered around continuously informing the process—to accelerate deployment timelines and introduce performance improvements. Image: Adam Malin, ORNL

Soon after Enrico Fermi’s Chicago Pile-­1 went critical for a brief duration in December 1942, the construction of the first continuously operating reactor, the X-­10 Graphite Reactor, was initiated in February 1943 at Clinton Engineer Works in Oak Ridge, Tenn. On November 4 of that year, a mere nine months after the start of construction, the reactor began operation. This marked the onset of what Alvin M. Weinberg referred to as “the first nuclear era,” during which many reactors of various designs and operating parameters were built and demonstrated across the United States. Forty years ago, the Fast Flux Test Facility was the last U.S. non-­light-­water reactor to reach criticality, and it has since been decommissioned.

A report released to the public on February 20 by the Government Accountability Office concluded that maintenance inspections at several contaminated excess facilities at the Department of Energy’s Hanford Site, near Richland, Wash., have not been comprehensive and that there are areas of some facilities that personnel infrequently or never enter, either physically or by remote means, to conduct inspections. The GAO reviewed surveillance and maintenance (S&M) requirements and activities at 18 of Hanford’s approximately 800 excess facilities that require cleanup and found that improvements to the site’s S&M program are needed.

The United States is pursuing the objective to land humans more than 100 million miles away on Mars, and nuclear power has the potential to be a key technology in getting to the Red Planet and providing power while there. Specifically, nuclear thermal propulsion (NTP) is a promising approach that could enable astronauts to travel from Earth’s orbit to Mars and back in a fraction of the time, and with greater safety, than is available with other options.

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.

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.