Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Wilmarth, W.R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, M.R.; Thompson, M.C.; Suggs, Patricia C.; Machara, Nicholas P.

doi:10.1080/07366299.2011.539134

Cited by 122 publications

(95 citation statements)

References 49 publications

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“…18 and 19, which are the overlays of the AN-102 and AZ-102 results for f SO 3 ,insol and f Re,insol given in Fig. 8(c) and Fig.…”

Section: Re Partitioning and Retentionmentioning

confidence: 95%

“…The mass fraction of SO 3 and Re in the insoluble phase (f SO 3 ,insol and f Re,insol ) as a function of temperature are shown in Figs. 18 and 19, which are the overlays of the AN-102 and AZ-102 results for f SO 3 ,insol and f Re,insol given in Fig.…”

Section: Re Partitioning and Retentionmentioning

confidence: 99%

“…The current cleanup plan is to separate the tank wastes into high-volume, low-activity waste (LAW) and low-volume, high-level waste (HLW) fractions that will then be vitrified into separate glass waste forms for long-term storage [1][2][3]. The LAW, a processed aqueous solution from tanks, primarily consists of sodium nitrates and nitrites with other salts/hydroxides and organics that vary from tank to tank (see an example composition given in Schonewill et al [4]).…”

Section: Introductionmentioning

confidence: 99%

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Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Jin

Kim

Tucker

et al. 2015

Journal of Non-Crystalline Solids

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a b s t r a c tVolatile loss of radioactive technetium-99 ( 99 Tc) to off-gas is a major challenge when vitrifying low-activity waste (LAW) at the U.S. Department of Energy's Hanford Site in Washington State. We investigated the partitioning and incorporation of rhenium (Re) (a nonradioactive surrogate for 99 Tc) into the glass melt during crucible melting of two simulated LAW feeds that have exhibited a large difference in 99m Tc/Re retention in glass from small-scale melter tests. Each feed was prepared from a simulated liquid LAW and additives (boric acid, silica sand, etc.). The as-mixed slurry feeds were dried at 105°C and heated to 600-1100°C at 5 K/min. The dried feeds and heat-treated samples were leached with deionized water for 10 min at room temperature followed by 24-h leaching at 80°C. Chemical compositions of the resulting solutions and insoluble solids were analyzed. Volume expansion measurements and X-ray diffraction (XRD) analyses were performed on dried feeds and heat-treated samples to characterize the progress of feed-to-glass conversion reactions. We found that incorporation of Re into the glass melt was virtually completed during the major feed-to-glass conversion reactions that occurred at ≤700°C. The results of our study suggest that the different compositions of the salt phases formed during early stages of melting at ≤700°C are responsible for the large difference in Re incorporation into the glass melt in these two feeds.

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“…18 and 19, which are the overlays of the AN-102 and AZ-102 results for f SO 3 ,insol and f Re,insol given in Fig. 8(c) and Fig.…”

Section: Re Partitioning and Retentionmentioning

confidence: 95%

Section: Re Partitioning and Retentionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Jin

Kim

Tucker

et al. 2015

Journal of Non-Crystalline Solids

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“…When the pH value is higher than 6, AMP would also decompose (Miller and Brown, 1997). Bentonite is a kind of clay, mainly composed of montmorillonite (Wilmarth et al, 2011), that has a huge specific surface area, and for bentonite, unequal cation exchange can be easily conducted in its interlayer, leading to a durable negative charge. Therefore, bentonite shows a relatively high cation exchange capacity and a stronger absorbability (Zhu, 2009), which could be used for the treatment of 137 Cs þ / 90 Sr 2þ -containing nuclear industrial waste liquid.…”

Section: Introductionmentioning

confidence: 99%

Adsorption Kinetics of ¹³⁷Cs⁺/⁹⁰Sr²⁺ on Ca‐Bentonite

Wang

Chu

Chen

2017

Water Environment Research

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137Cs+/90Sr2+ adsorption kinetics on natural Ca-bentonite under the impact of different adsorption conditions was examined in detail. The results indicate that natural Ca-bentonite shows a strong adsorption capacity for Cs+/Sr2+. The adsorption reached at equilibrium after 2 hours for Cs+. Cs+/Sr2+removal efficiency reaches the highest when the pH value is 5 to 8 and increases with the increase of Ca-bentonite adding amount. Cs+ removal efficiency increases with the increase of Cs+ initial concentration, while Sr2+ removal efficiency slightly varies around 70%. The adsorption of Cs+/Sr2+ by Ca-bentonite follows the pseudo-second-order model and is controlled by chemical adsorption. Meanwhile, the results of intraparticle diffusion modelling indicate that intraparticle diffusion is a kinetics controlling step, besides surface adsorption and liquid film diffusion.

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“…The most common metal in the Hanford waste is 27 Al, and the elements responsible for most radioactivity are 90 Sr and 137 Cs. The requirement for disposal is that the 90 Sr activity be less than 20 Ci/m 3 , while on average the waste contains 240 Ci/m 3 [14]. For 137 Cs, the feed has about 230 Ci/m 3 , and limit is set by the Department of Energy at 0.105 Ci/m 3 to reduce radiation exposure to personnel.…”

Section: Nuclear Wastementioning

confidence: 99%

Metrics For Comparing Plasma Mass Filters

Fisch¹

2012

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High-throughput mass separation of nuclear waste may be useful for optimal storage, disposal, or environmental remediation. The most dangerous part of nuclear waste is the fission product, which produces most of the heat and medium-term radiation. Plasmas are well-suited to separating nuclear waste because they can separate many different species in a single step. A number of plasma devices have been designed for such mass separation, but there has been no standardized comparison between these devices. We define a standard metric, the separative power per unit volume, and derive it for three different plasma mass filters: the plasma centrifuge, Ohkawa filter, and the magnetic centrifugal mass filter.

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Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Cited by 122 publications

References 49 publications

Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Adsorption Kinetics of ¹³⁷Cs⁺/⁹⁰Sr²⁺ on Ca‐Bentonite

Metrics For Comparing Plasma Mass Filters

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Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Cited by 122 publications

References 49 publications

Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Reactions during melting of low-activity waste glasses and their effects on the retention of rhenium as a surrogate for technetium-99

Adsorption Kinetics of 137Cs+/90Sr2+ on Ca‐Bentonite

Metrics For Comparing Plasma Mass Filters

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Product

Resources

About

Adsorption Kinetics of ¹³⁷Cs⁺/⁹⁰Sr²⁺ on Ca‐Bentonite