Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

Cochran, John R.; Brown, Theresa J.; Stockman, Harlan W.; Gallegos, D.P.; Conrad, Stephen H.; Price, L.L.

doi:10.2172/537284

Cited by 2 publications

(3 citation statements)

References 7 publications

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“…In 1995, SNL was asked to evaluate the GCD boreholes at Nevada National Security Site for the disposal of vitrified Fernald byproduct material, and in 1997 SNL completed a preliminary PA (Cochran, Brown, et al 1997) that identified several issues; however, a full PA has not been conducted to date.…”

Section: Significance Of Yucca Mountain Repository Pa In the Historicalmentioning

confidence: 99%

“…In 1997 SNL completed a preliminary, or scoping, PA which included a description of the approach, regulatory analysis, selection of performance objectives, site and waste description, preliminary modeling results, and identification of issues and activities required to complete a full PA (Cochran, Brown, et al 1997). Since this was not a full PA and it did not follow the probabilistic methodology, it will only be described briefly here.…”

Section: Demonstration For Vitrified Fernald Waste (1997)mentioning

confidence: 99%

See 1 more Smart Citation

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

Marietta¹,

Anderson²,

Bonano³

et al. 2011

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Section: Significance Of Yucca Mountain Repository Pa In the Historicalmentioning

confidence: 99%

Section: Demonstration For Vitrified Fernald Waste (1997)mentioning

confidence: 99%

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

Marietta¹,

Anderson²,

Bonano³

et al. 2011

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“…Current plans (Cochran et al, 1995) call for disposal of the Fernald glass at the Radioactive Waste Management Site (RWMS), located in the Nevada Test Site (NTS) in Southern Nevada. The waste may be placed either in 40 m deep boreholes, or 7 m deep trenches dug in the alluvium.…”

Section: Likely Disposal Environmentmentioning

confidence: 99%

Long-term modeling of glass waste in portland cement- and clay-based matrices

Stockman¹,

Nagy²,

Morris³

1995

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A set of "templates" was developed for modeling waste glass interactions with cementbased and clay-based matrices. The templates consist of a modified thermodynamic database, and input files for the EQ3/6 reaction path code, containing embedded rate models and compositions for waste glass, cement, and several pozzolanic materials. Significant modifications were made in the thermodynamic data for Th, Pb, Ra, Ba, cement phases, and aqueous silica species. It was found that the cement-containing matrices could increase glass corrosion rates by several orders of magnitude (over matrixless or clay matrix systems), but they also offered the lowest overall solubility for Pb, Ra, Th and U. Addition of pozzolans to cement decreased calculated glass corrosion rates by up to a factor of 30. It is shown that with current modeling capabilities, the "affinity effect" cannot be trusted to passivate glass if nuclei are available for precipitation of secondary phases that reduce silica activity. 4.1 THERMODYNAMIC DATA 10

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Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

Cited by 2 publications

References 7 publications

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

Long-term modeling of glass waste in portland cement- and clay-based matrices

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