Historic research division continues to push nuclear frontiers
ARGONNE, Ill. (Sept. 6, 2004) – The building housing Argonne's Chemical
Engineering Division (CMT) was named
a Nuclear Historic Landmark this summer by the American
Nuclear Society. The
award recognizes the division's significant contributions to the development,
implementation and peaceful use of nuclear technology.
“Nuclear energy for the power industry started here at Argonne,” said David
Lewis, CMT director. “We're part of that.”
Since Argonne's opening 58 years ago, CMT has been developing processes for
reducing nuclear waste volume and recovering valuable elements from spent reactor
fuel. Some techniques allow parts of the fuel to be reused.
The division continues its key role in the nation's energy future through
its research into nuclear waste separation techniques. CMT engineers and chemists
have developed both aqueous and non-aqueous methods to separate and reduce
waste created in nuclear reactors.
Current work is part of the Advanced
Fuel Cycle Initiative, which aims to
reduce the nation's nuclear waste and extend the capacity of the Yucca
Mountain repository. The goal is to delay or even avoid the multi-billion dollar cost
of a second repository.
“This waste is an international concern,” said CMT's Jim Laidler, who serves
as a technical director for the U.S. Department
of Energy's chemical separations
program. “Separating the elements of spent nuclear fuel reduces the amount
of high-level waste requiring long-term storage in a geologic repository.”
Aqueous separations
CMT's first foray into radionuclide separation was aqueous processing to separate
uranium and plutonium from dissolved irradiated fuel. The REDOX process Argonne
helped to design replaced an expensive, waste-intensive operation at DOE's
Hanford Site in Washington State. Cost savings from REDOX paid for a new $50-million
REDOX plant.
CMT also played a key role in developing next-generation solvent-extraction
methods, including PUREX and TRUEX.
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Key contactor
The workhorse behind the division’s solvent extraction research is a centrifugal
contactor designed more than 30 years ago.
The device is a cylindrical rotor surrounded by a mixing bowl. The spinning
rotor acts as a mixer, a centrifugal settler and a pump. The liquid waste
and solvent enter the bowl from opposite directions, and the rotor mixes
them, allowing the solvent to extract the material to be removed. The liquids
enter the hollow spinning rotor, and centrifugal forces 100 to 400 times
gravity separate the liquids, which leave through separate ports at the
rotor’s
top.
The centrifugal contactors are efficient. They use only about one gallon
of solvent per 3,000 gallons of waste.
The contactor has been used at
many DOE facilities including
Pacific Northwest, Los Alamos
and Oak Ridge
national laboratories, the
Oak Ridge Y-12 Plant, the Hanford Site
and the Idaho National Engineering and Environmental Laboratory. |
More recently, CMT – in cooperation with teams at Oak
Ridge and Savannah River national
laboratories and the Savannah River Site – developed a process called
caustic-side solvent extraction (CSSX). CSSX combines CMT's centrifugal contactor
(see sidebar) with a highly selective solvent developed at Oak Ridge.
CSSX has been chosen by DOE to reduce by 15-fold the volume of radioactive
cesium-137 from tank waste created as a by-product of defense activities.
The cesium will then be incorporated into a glass waste form for disposal in
a geologic repository. The remaining material can be disposed of as low-level
radioactive waste.
In tests at Argonne, CSSX extracted all but one part in 150,000 of
the original cesium in test samples, which is better than DOE required.
UREX+ is CMT's current aqueous research success. UREX+ is a four-step process
CMT researchers designed and demonstrated to separate the components of light-water
reactor fuel created by commercial reactors. The first step removes uranium
(about 96 percent of the waste mass) for disposal as low-level waste. The second
step separates cesium and strontium from for decay storage. In the third step,
plutonium and neptunium are removed for recycling into light-water-reactor
fuel (they are destroyed as they burn, making them unavailable for weapons
use). The fourth step removes americium and curium for storage and eventual
destruction in advanced reactors.
Pyrochemical separations
While UREX+ can process spent commercial fuel and recycle some of it into
fuel for today's commercial light-water reactors, pyrochemical separation processes
are being developed to support the future U.S. nuclear enterprise.
In the late 1950s, chemical engineers began developing pyrochemical methods
to separate nuclear waste products created by Argonne's Experimental Breeder
Reactor-II. These early methods relied on extraction techniques similar to
those used in aqueous processing but were conducted using molten salts and
liquid metals. A melt-refining technique was developed and used to treat approximately
five tonnes of EBR-II fuel, and research on pyrochemical processes has continued
to evolve over the years as part of Argonne's advanced reactor programs.
Recent developments rely on electrochemical rather than extraction methods
that use chemical reagents to separate materials from irradiated fuel. This
avoids the additional waste stream associated with using chemical reagents.
Electrorefining, which recovers uranium from spent fuel, was developed to close
the fuel cycle for the Integral Fast Reactor, an advanced fast reactor technology
Argonne developed in the 1984-1994 period, and is now used to condition spent
fuel from EBR-II.
Advancement of electrorefining technology continues with the development of
the Planar Electrode ElectoRefiner (PEER). PEER's design eases materials
handling requirements (which is important in a remotely operated facility),
facilitates scaling to achieve fuel throughput goals, and provides a means
for electrorefining to transition from a batch process to a continuous process.
Like the aqueous UREX+ process, electrorefining separates uranium into one
separate stream. But electrorefining keeps the plutonium and neptunium with
the americium and curium, which are recovered in a subsequent pyroprocess,
recycled into advanced reactor fuel, and destroyed as they produce electricity.
In addition, keeping the plutonium with the other elements eases nuclear proliferation
concerns by making it unsuitable for direct use in nuclear weapons. Pyrochemical
processing may also reduce the cost of treating spent fuel and provide greater
flexibility in the deployment of fuel treatment facilities.
Argonne's aqueous and non-aqueous processes both have attracted international
attention from such nations as France, Japan, Russia, South Korea and the
United Kingdom, which have growing amounts of spent fuel for disposal.
Argonne's CMT Division continues its research into both aqueous and pyrochemical
processes because part of the division's mission is to provide innovative solutions
to the challenges created by powering our nation with nuclear-based energy.
UREX+ offers a way to recycle spent fuel from light-water reactors and decrease
the amount of high-level waste needing storage in a geological repository.
Pyroprocessing technologies can provide a bridge to the next generation of
nuclear power plants. — Evelyn Brown
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