The 13th International Conference on Environmental ... - Events

Abstracts
size-reduced to get them out of the glovebox. <strong>The</strong> task is a high-risk operation because the glass shards that are generated
can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker’s skin when completing the task. One
of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and
provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these
enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively
permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into
a container for removal from the glovebox as non-compactable transuranic (TRU) waste. This size-reduction operation
reduces solid TRU waste volume generation by almost 2½ times. Replacing one-time-use bag-out bags with multiple-use
glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination,
cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National
Laboratory Continuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox
operations. In this report, the technical issues, associated with implementing this process improvement are addressed, the
results discussed, effectiveness of Lessons Learned evaluated, and waste savings presented.
5) 40247 – Disposition of Transuranic Residues from Plutonium Isentropic Compression Experiment (Pu-ICE).
LA-UR 10-04699.
Kapil Goyal, David M. French, LANL (USA); Betty J. Humphrey, Weston Solutions, Inc. (USA);
Jeffry Gluth, Sandia National Laboratories/NM (USA)
In 1992, the U.S. Congress passed legislation to discontinue above- and below-ground testing of nuclear weapons.
Because of this, the U.S. Department of Energy (DOE) must rely on laboratory experiments and computer-based
calculations to verify the reliability of the nation’s nuclear stockpile. <strong>The</strong> Sandia National Laboratories/New Mexico
(SNL/NM) Z machine was developed by the DOE to support its science-based approach to stockpile stewardship.
SNL/NM researchers also use the Z machine to test radiation effects on various materials in experiments designed
to mimic nuclear explosions. Numerous components, parts, and materials have been tested. <strong>The</strong>se experiments use a
variety of radionuclides; however, plutonium (Pu) isotopes with greater than ninety-eight percent enrichment are the
primary radionuclides used in the experiments designed for stockpile stewardship. In May 2006, SNL/NM received
authority that the Z Machine Isentropic Compression Experiments could commence.
Los Alamos National Laboratory (LANL) provided the plutonium targets and loaded the target assemblies, which
were fabricated by SNL/NM. LANL shipped the loaded assemblies to SNL/NM for Z machine experiments. Three
experiments were conducted from May through July 2006. <strong>The</strong> residues from each experiment, which weighed up to 913
pounds, were metallic and packaged into a respective 55-gallon drum each. Based on a memorandum of understanding
between the two laboratories, LANL provides the plutonium samples and the respective radio-isotopic information.
SNL/NM conducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste
certification for disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a
comprehensive approach for documenting generator knowledge for characterization of waste in cooperation with
scientists at the two laboratories and addresses a variety of topics such as material control and accountability, safeguards
of material, termination of safeguards for eventual shipment from SNL/NM to LANL, associated approvals from
DOE-Carlsbad Field Office, which governs WIPP and various notifications. It portrays a comprehensive approach
needed for successful completion of a complex project between two national laboratories.
6) 40188 – A Milestone in Vitrification - the Replacement of a Hot Metallic Crucible with a Cold Crucible
Melter in a Hot Cell at the La Hague Plant
Sphiee Robert, Benoit Carpentier,SGN (France); Florence Gassot Guilbert, SGN Service procédé (France);
Sandrine Naline, AREVA (France); Frédéric Gouyaud, AREVA NC (France); Christophe Girold, CEA (France)
Vitrification of high-level waste is the internationally recognized way to optimize the conditioned High Level Waste
to be disposed of.
AREVA’s successful operation of AVM at the Marcoule plant, R7 and T7 at the La Hague Plants demonstrates the
capabilities and experience of the Group to deploy innovative high level waste (HLW) processing technologies in
industrial facilities, in partnership with R&D (CEA) and AREVA engineering (SGN). CEA and AREVA engineering
team have continuously improved the hot metallic crucible melter vitrification technology through operational feedback
aswell as ongoing research and developement. <strong>The</strong>y have led the way in the development and implementation of Cold
Crucible Induction Melter technology (CCIM).
<strong>The</strong> cold crucible is a compact water-cooled melter in which the radioactive waste and the glass are molten by direct
high frequency induction. This technology can handle with highly corrosive solutions and high operating temperature,
which offers, among others advantages: o a great flexibility in matrix compositions, o the increase of the industrial glass
production capacity, ° increase of melting temperature, ° allow higher waste loading, ° extend to a wide and varied waste
types
In order to take advantage of CCIM, a new project, called “Vitrification 2010”, was launched in 2005 with the
objective to put in commercial operation a CCIM in one of the existing and active R7 vitrification line in 2010. <strong>The</strong> main
challenge for the project team is to replace the hot metallic crucible melter with the CCIM: o in an existing hot cell which
is in operation for 20 years with high level waste solutions, o with respect to the current hot cell’s layout (calciner,
through-wall for utility for example…).
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