Preliminary waste form characteristics report Version 1.0. Revision 1

Stout, R.B.; Leider, H.R.

doi:10.2172/61004

Cited by 7 publications

(12 citation statements)

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“…The maximum concentration of plutonium at the ER-20-5 site is about lE-14 M , which is lower than solubility limits experimentally determined (-E-8 M) for plutonium (V) species likely to be present in NTS groundwater (Nitsche et al, 1993) and near the solubility limits calculated (-lE-12 M to IE-17 M) assuming thermodynamic equilibrium for plutonium (IV) (Stout and Leider, 1994) (Guillaumont and Adloff, 1992). Due to the very low concentration of plutonium measured in the groundwater at ER-20-5, it is unlikely that the plutonium was above the solubility limit and precipitated as a solid phase.…”

Section: Discussioncontrasting

confidence: 57%

Hydrologic resources management program and underground test area operable unit fy 1997

Smith¹

1998

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Section: Discussioncontrasting

confidence: 57%

Hydrologic resources management program and underground test area operable unit fy 1997

Smith¹

1998

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“…The maximum measured concentration of Pu at the ER-20-5 site is ,10 -14 M. This value is lower than the solubility limits of ,10 -8 M that have been experimentally determined for the Pu (V) species likely to be present in NTS ground water 4 . The calculated solubility limits (10 -12 ±10 -17 M), obtained by assuming that Pu(IV) is in thermodynamic equilibrium 26,27 , bracket the maximum measured Pu concentration. It thus seems that the Pu concentrations in the ground water at ER-20-5 were too low to lead to the precipitation of a solid Pu phase.…”

mentioning

confidence: 84%

Migration of plutonium in ground water at the Nevada Test Site

Kersting

Efurd

Finnegan

et al. 1999

Nature

896

604

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Re and Al 2 O 3 were heated with laser beams from both sides. Acting like planar heat sources, the two`hot plates' eliminate the axial temperature gradient in the sample between the plates. Temperature variation is less than 3% within roughly 30 mm diameter at 2,500 K. Before the melting experiments, the sample was scanned with a laser beam and heated to about 2,000 K to reduce the pressure gradient and to produce a high-pressure solid-phase assemblage. For stable and smooth temperature control, temperatures were increased by adjusting an aperture placed near the beam exit, stepwise, instead of by adjusting power. Each step corresponds to a 50±100 K increase. A 30-mm spot was homogeneously heated by opening the aperture (increasing the step). At the onset of melting, temperature remains constant or drops slightly with the step increment, and then drastically increases (.400 K) within one step. To ensure the reliability of the melting criteria used in this study, we conducted melting experiments at pressures (16±27 GPa) overlapped by the multi-anvil apparatus and the diamond-anvil cell, using the same starting material, and obtained consistent melting temperatures (Fig. 3). We also used the same melting criteria to determine the melting temperature of MgSiO 3 ±perovskite previously studied by other investigators, and our results agree with these recent determinations 13,14 (Fig. 3). The temperature runaway phenomena near the onset of melting observed in simple and complex samples were probably a result of the latent heat of melting, followed by melt migrating away from the heated spot because of the large thermal pressure and, ®nally, the Re foils would have been heated without sample in between. No chemical reaction between Re and sample was observed in the multi-anvil experiments on a scale of 1 mm. The melting temperatures reported here are the last temperatures before melting sets in. Pressures were measured using a ruby-¯uorescence technique after each measurement of melting temperature.

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“…The investigated configurations of the waste package are outlined in Section 5. 4 M&O (1999b) and Stout and Leider (1991), respectively. The Savannah River Site high-level waste glass canister dimensions are from Taylor (1997).…”

Section: Calculationmentioning

confidence: 99%

Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container

Moscalu¹

2002

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Preliminary waste form characteristics report Version 1.0. Revision 1

Cited by 7 publications

References 0 publications

Hydrologic resources management program and underground test area operable unit fy 1997

Hydrologic resources management program and underground test area operable unit fy 1997

Migration of plutonium in ground water at the Nevada Test Site

Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container

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