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Dry Casks 101: What Do Robots Have to do With Dry Cask Storage?

Darrell Dunn
Materials Engineer

CASK_101finalCutting-edge robot technology is making it easier to inspect inside spent fuel dry cask storage systems.

You may remember from past blog posts that most spent fuel dry cask storage systems, or casks, consist of stainless steel canisters that are welded shut to safely contain the radioactive contents. The canisters are in turn placed inside thick storage overpacks to shield plant workers and the public from radiation. As these casks remain in use for longer time frames, the ability to inspect canister surfaces and welds will become an important aspect of the NRC’s confidence in their safety.

To be clear: techniques for inspecting canister surfaces and welds have been used for decades. These techniques are collectively known as nondestructive examination (NDE) and include a variety of methods, such as visual, ultrasonic, eddy current and guided wave examinations.

img2 (002)Where do robots come in? They are a delivery system. Robots are being developed to apply these NDE techniques inside casks. Not just any robot will do. These robots need to fit into small spaces and withstand the heat and radiation inside the cask. The state-of-the-art is evolving quickly.

To date, the Electric Power Research Institute and cask manufacturers have successfully demonstrated robotic inspection techniques to NRC staff three times: at the Palo Verde plant in Arizona (Sept. 2-3, 2015), at the McGuire plant in North Carolina (May 16-19, 2016), and just last month, at Maine Yankee (July 12-13, 2016).

At Palo Verde, the robot was used to deliver eddy current testing instrumentation inside a cask. Eddy current testing detects variations in electromagnetically induced currents in metals. Because it is sensitive to surface defects, eddy current testing is a preferred method for detecting cracks. The inspection robot was used to examine part of the mockup canister fabrication weld. An EPRI report provides a detailed description of the Palo Verde test. Future reports are expected on the McGuire and Maine Yankee demonstrations. These demonstrations are helping to refine the robots’ designs.

Cutaway Cask Mockup with Robot (002)The Maine Yankee demo was conducted in July 2016 on a cask loaded in 2002. The demo involved a robot maneuvering a camera with a fiber optic probe, which meets the industry code for visual examinations, inside the cask. The probe was able to access the entire height of the canister, allowing the camera to capture images of the fabrication and closure welds. The welds showed no signs of degradation. The canister was intact and in good condition.

The robot was also able to obtain samples from surfaces of the cask and canister. These samples are being analyzed for atmospheric deposits that could cause corrosion.

Ultimately, if degradation is identified, cask users would select their preferred mitigation and repair option.  They would have to meet the NRC’s safety requirements before implementing it.

Cask inspections are important to ensure continued safe storage of spent nuclear fuel and robots will continue to be a helpful tool in this important activity.

Dry Cask 101 – Radiation Shielding

Drew Barto
Senior Nuclear Engineer

CASK_101finalWe’ve talked before about how the uranium in nuclear fuel undergoes fission during reactor operations. The fission process turns uranium into a number of other elements, many of which are radioactive. These elements continue to produce large amounts of radiation even when the fuel is no longer supporting a chain reaction in the reactor. So shielding is necessary to block this radiation, and protect workers and the public.

As we discussed in an earlier blog post, the four major types of radiation differ in mass, energy, and how deeply they penetrate people and objects. Alpha radiation—particles consisting of two protons and two neutrons—are the heaviest type. Beta particles—free electrons—have a small mass and a negative charge. Neither alpha nor beta particles will move outside the fuel itself.

drycaskshieldingBut spent fuel also emits neutron radiation (particles from the nucleus that have no charge) and gamma radiation (a type of electromagnetic ray that carries a lot of energy). Both neutron and gamma radiation are highly penetrating and require shielding.

Shielding is a key function that dry storage casks perform, but the two main types of dry storage casks are configured in slightly different ways.

For welded, canister-based systems, shielding is provided by a thick (three feet or more) steel-reinforced concrete vault that surrounds an inner steel canister. The thick concrete shields both neutron and gamma radiation, and may be oriented either as an upright cylinder or a horizontal building.

In bolted cask systems, there is no inner canister. Bolted casks have thick steel shells, sometimes with several inches of lead gamma shielding inside. They have a neutron shield on the outside consisting of low-density plastic material, typically mixed with boron to absorb neutrons.

drycask101_radiationshielding_CompimagesThe NRC reviews spent fuel dry cask storage designs to ensure  they meet our limits on radiation doses beyond the site boundary, under normal and accident conditions, and that dose rates in general are kept as low as possible. Every applicant must provide a radiation shielding analysis as part of the application for a new storage system, or an amendment to an existing system. This analysis uses a computer model to simulate radiation penetration through the fuel and thick shielding materials under normal operating and accident conditions.

We review the applicant’s analysis to ensure it has identified all the important radiation-shielding parameters. We make sure they’re modeled conservatively, in a way that maximizes radiation sources and external dose rates. We may create our own computer simulation to confirm the dose rates provided in the application. That helps us to ensure the design meets off-site radiation dose rate requirements under all conditions.

A Bit of NRC Myth Busting — Part II

Eric Stahl
Acting Public Affairs Officer

 Facebook1As we said in yesterday’s Part I, we’ve taken a few of the interesting comments we’ve received on our Facebook page and posed them to our experts for their take on the question, suggestion or assertion. Here are their responses.

One user had several ideas for dealing with spent fuel including “mixing it in glass” and then burying it “in ice in Antarctica” or “blasting the glass off to Venus or Mars.”

 Mixing spent fuel with glass, a process known as “vitrification,” is one method that has been tested to treat nuclear waste in several countries. The idea supposes that mixing radioactive waste with other materials will create a more stable solution that won’t degrade over time.

??????In the U.S., over 50 million gallons of liquid waste from plutonium production at the Hanford site in Washington State will be vitrified and then stored onsite. DOE, who is responsible for oversight at Hanford, expects radioactivity levels in the material to greatly reduce in the future. If the country’s nuclear waste disposal policy was to turn toward vitrification, an application would need to come from the Department of Energy to the NRC. The NRC would be responsible for regulation.

However, burying vitrified spent fuel in Antarctica isn’t an option. Article V of the Antarctic Treaty of 1959, which the U.S. signed, prohibits the disposal of nuclear waste in Antarctica.

PrintSending vitrified spent fuel into space would be a risky and prohibitively expensive idea. According to NASA, it costs approximately $10,000 per pound to send things into orbit. Considering there’s currently more than 70,000 tons of spent fuel in the United States, shooting it into space wouldn’t be cost effective. In addition, a catastrophic accident involving a spacecraft hauling nuclear waste into space could cause radioactive material to contaminate the environment.

In any event, U.S. policy for spent fuel disposal is to place it in a deep geologic repository. Until and unless Congress changes the law, that will remain the policy.

And, finally, there are multiple comments about the wisdom and benefit of new reactor designs, especially one using fissile uranium salt.

The NRC is working to ensure we have the expertise available to review future advanced reactors (such as molten salt or high-temperature gas designs). The NRC will determine if those future designs are acceptable for U.S. use, and we’re working with the Department of Energy to inform advanced reactor designers how the review process will work. The NRC’s role, though, is regulating new designs, not initiating them.

A Bit of NRC Myth Busting — Part I

Eric Stahl
Acting Public Affairs Officer

Facebook1We’ve taken a few of the interesting comments we’ve received on our Facebook page and posed them to our experts for their take on the question, suggestion or assertion. Here are their responses.

One Facebook user suggested that nuclear waste could be “encased in thick high strength concrete, then dropped into a churning volcano. It would sink into the magma and over a time it would disperse.” (We took the liberty of cleaning up the typos.)

Spent fuel must be handled and stored with care due to its radioactivity. The only way radioactive waste becomes harmless is through decay, which can take hundreds of thousands of years. As a result, the waste must be stored and disposed of in a way that provides protection to the public for a very long time.

PrintDropping spent fuel into an active volcano would run counter to this idea. Radioactive material could be released into the atmosphere, causing a hazard to people and the environment.

Another Facebook user, on our post about renewing licenses for nuclear power plants beyond the original license renewal, wrote this: “Beyond 60 years They are about to blow now you idiots.”

Contrary to what Hollywood often presents in television and movies, U.S. nuclear reactors are designed with numerous safety features, including containment buildings that continue to protect people and the environment. The nuclear fuel can’t explode, and many reinforcing safety systems would prevent or control the buildup of flammable gases during an accident.

NRC inspectors spend more than 6,000 hours (on average) performing inspection-related activities at each reactor site. In addition, the NRC has a robust aging management program to ensure that the country’s oldest reactors continue to operate safely. Keep in mind that regardless of the age of any reactor, the NRC has authority to address safety issues at any time.

Another Facebook commenter had concerns about the current dry cask storage system. He writes: “All that nuclear waste is being stored in the ground in what is supposed to be 5000 year containers, what if an earthquake hit the storage facility?”

All nuclear waste storage containers, known as “casks,” that are used to store spent fuel in the United States undergo a thorough safety review by the NRC before they’re certified for use. All casks licensed by the NRC must demonstrate their ability to withstand earthquakes and other natural hazards. Once the casks are put into use, they’re continuously monitored for leaks and periodically inspected by the NRC.

Come back tomorrow for Part II!

 

WCS Sends NRC Interim Storage Application

Mark Lombard
Director, Division of Spent Fuel Management

You may have heard that the NRC has received an application today for a centralized storage facility for spent nuclear fuel. We thought this would be a good time to talk about what that facility would do, and how we will review the application.

First some background. “Spent fuel” is the term we use for nuclear fuel that has been burned in a reactor. When spent fuel is removed from a reactor, it is very hot, so it is put immediately into an onsite pool of water for cooling. Initially, the plan in the ‘70s had been to send the spent fuel for “reprocessing” prior to final disposal, so usable elements could be removed and made into fresh fuel. But reprocessing fell out of favor in the United States in the ‘80s.

Officials from Waste Control Specialists deliver its application to construct and operate a consolidated interim storage facility to Joel Munday, Acting Deputy Director of the NRC’s Office of Nuclear Material Safety and Safeguards.

Officials from Waste Control Specialists deliver its application to construct and operate a consolidated interim storage facility to Joel Munday, Acting Deputy Director of the NRC’s Office of Nuclear Material Safety and Safeguards.

To manage their growing inventory, nuclear utilities turned to dry storage. The idea behind dry storage casks is to cool the fuel passively, without the need for water, pumps or fans. The first U.S. dry storage system was loaded in 1986. In the past 30 years, dry storage has proven to be safe and effective.

Against this backdrop, a Texas company, Waste Control Specialists (WCS), filed an application with us today for a dry cask storage facility to be located in Andrews County. WCS plans to store spent fuel from commercial reactors; initially, from reactors that have permanently shut down.

The application discusses utilizing dry storage casks that have previously been approved by the NRC. The spent fuel would arrive already sealed in canisters, so the handling would be limited to moving the canisters from transportation to storage casks.

Ever since Congress enacted the first law for managing spent nuclear fuel in 1982, federal policy has included some centralized site to store spent fuel before final disposal in a repository. Congress made DOE responsible for taking spent fuel from commercial reactors. It gave NRC the responsibility to review the technical aspects of storage facility designs to ensure they protect public health and safety and the environment.

We conduct two parallel reviews – one of the safety and security aspects, the other of potential environment impacts.

But before those reviews get underway, we will review the application to see if it contains enough information that is of high enough quality to allow us to do the detailed reviews. If it doesn’t, WCS will have a chance to supplement it. If we find the application is sufficient and accept it, we will publish a notice in the Federal Register. This notice will alert the public that we have accepted the application for technical review, and offer an opportunity to ask for a hearing.

Then we begin our reviews. At the beginning of our safety and security review, NRC staff will hold a public meeting near the site to answer questions about our process. We’ll also have public meetings with WCS as needed so the staff can ask questions about the application. We will document this review in a Safety Evaluation Report.

Once we get public and stakeholder input on the scope of our environmental review, we will conduct the review and document the results in a draft Environmental Impact Statement (EIS). We’ll ask the public and stakeholders to comment on the draft. After considering those comments, we’ll finalize it.

We expect the review process to take us about three years, assuming WCS provides us with good information in a timely way during our review.

If interested parties ask for a hearing, and their petition is granted by our Atomic Safety and Licensing Board, then the board will consider specific “contentions,” or challenges to our reviews of the safety, security or environmental aspects of the proposed facility. The board will hold a hearing on any contentions that cannot be resolved. We can’t predict how long this hearing process would take.

The Safety Evaluation Report, the EIS and the hearing need to be complete before the NRC staff can make a licensing decision. If the application meets our regulations, we’re legally bound to issue a license. We don’t consider whether there’s a need for the facility or whether we think it’s a good idea. Our reviews look at the regulatory requirements, which are carefully designed to ensure public health and safety will be protected, and at the potential environmental impacts and applicant’s plans for mitigating them.

Incidentally, we are expecting an application for a second centralized interim storage facility Nov. 30. This one, to be filed by Holtec International, will be for a site in New Mexico. We’ll follow the same process in reviewing that application.

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