The Sort on Radioactive Waste Type model: A method to sort single-shell tanks into characteristic groups. Revision 2

Hill, J.G.; Anderson, G.S.; Simpson, B.C.

doi:10.2172/32782

Cited by 8 publications

(2 citation statements)

References 3 publications

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“…The actual tank waste leach testing program was limited to eight groups that would account for ∼75 wt % of the materials of interest in the expected feeds to the WTP with respect to leaching (tank waste Best Basis Inventory): , …”

Section: Experimental Materialsmentioning

confidence: 99%

Leaching Characteristics of Hanford Ferrocyanide Wastes

Edwards

Fiskum

Shimskey

et al. 2009

Ind. Eng. Chem. Res.

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A series of leach tests were performed on actual Hanford Site tank wastes in support of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The samples were targeted composite slurries of high-level tank waste materials representing major complex, radioactive, tank waste mixtures at the Hanford Site. Using a filtration/leaching apparatus, sample solids were concentrated, caustic leached, and washed under conditions representative of those planned for the Pretreatment Facility in the WTP. Caustic leaching was performed to assess the mobilization of aluminum (as gibbsite, Al[OH]3, and boehmite AlO[OH]), phosphates [PO4 3−], chromium [Cr3+], and, to a lesser extent, oxalates [C2O4 2−]). Ferrocyanide waste released solid phase 137Cs during caustic leaching; this was antithetical to the other Hanford waste types studied. Previous testing on ferrocyanide tank waste focused on the aging of the ferrocyanide salt complex and its thermal compatibilities with nitrites and nitrates. Few studies, however, examined cesium mobilization in the waste. Careful consideration should be given to the pretreatment of ferrocyanide wastes in light of this new observed behavior, given the fact that previous testing on simulants indicates a vastly different cesium mobility in this waste form. The discourse of this work will address the overall ferrocyanide leaching characteristics as well as the behavior of the 137Cs during leaching.

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Section: Experimental Materialsmentioning

confidence: 99%

Leaching Characteristics of Hanford Ferrocyanide Wastes

Edwards

Fiskum

Shimskey

et al. 2009

Ind. Eng. Chem. Res.

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“…On Radioactive Waste Type (SORWT) Group Model Validation. The goal of this activity is to study the validity of using the SORWT grouping model (Hill et al 1995) to extrapolate ESW data obtained from representative tanks to untested and uncharacterized SSTs. The SORWT group model validation does not at this time require any sampling activities.…”

Section: Sortmentioning

confidence: 99%

Tank characterization technical sampling basis

Brown¹

1998

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The Hanford Site has 177 underground high-level radioactive waste storage tanks in 18 tank farms. The tanks contain accumulated liquid, sludge, and saltcake wastes from more than 50 years of nuclear weapons material production activities at the Hanford Site. Several types of waste exist in the tanks, and the tank contents vary from homogeneous to highly heterogeneous. The tanks also have a variety of important safety, disposal, regulatory, and operational issues associated with them. In addition to the 177 tanks, several double-contained receiver tanks (DCRTs), catch tanks, and inactive miscellaneous underground storage tanks (IMUSTs) are also in the purview of Tank Waste Remediation Systems (TWRS).This document establishes an approach to determine the priority of tank sampling at the Hanford Site. The approach is based on data quality objectives (DQOs) and other requirements documents for each issue identified, as well as tank priority inputs from each of the TWRS programs. The DQOs (or other requirements documents) used to direct characterization for each of the issues are listed below:Flammable gas (Bauer and Jackson 1997) Sluicing of tank 241-C-106. The characterization requirements are documented in a process control plan (Carothers et al. 1998).Waste feed delivery (Phase I). Characterization requirements will be documented in problem-specific DQOs, one to confirm the selection of tanks to supply low-activity waste (Certa 1998) and one to confirm the selection of tanks to supply high-level waste, to be issued by May 1998 (problem-specific DQOs #1 and 2, respectively). Ten other problem-specific DQOs will be written (#3 -10 and 13 -14). A decision will be made Es-1 HNF-SD-WM-TA-164 Rev. 4 later to determine which of these 10 problem-specific DQOs will require characterization sampling, if any. Problem-specific DQO #11 will probably be canceled because its requirements are covered by the Privatization low-activity waste DQO (Wiemers and Miller 1997. See next bullet). Problem-specific DQO #12 will be canceled because no further information is required (Murkowski 1997). In addition to the problem-specific DQOs, the retrieval DQO (Bloom and Nguyen 1996) and the mixer pump test plan (Staehr 1996) will be used to direct sampling and analysis of tank 241-AZ-101. The retrieval DQO will be transitioned out of use, to be replaced by the problem-specific DQOs. The mixer pump test plan is being updated to ensure that required data will be obtained and that sufficient detail will be provided to direct sampling and analysis. HNF-SD-WM-TA-164 Rev. 4 HNF-SD-WM-TA-164 Rev. 4 PRIVATIZATION -Provide Samples To Contractor(s) CRITERIA WEIGHT C-104 C-106 AN-102 AN-103 AN-104 AN-105 AN-107 AW-IO1 Tank waste info needed H H

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