Results of dilution studies with waste from tank 241-AN-104

Herting, D.L.

doi:10.2172/782273

Cited by 27 publications

(92 citation statements)

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“…To ensure t h e best possible uniformity, a l l a l i q u o t s will be taken by syringe sampling while the composite sample i s being mixed. Duplicate t e s t s performed on s i m i l a r 105-AN samples (Herting 1997) showed t h a t t h i s sampling method gives acceptable r e p r o d u c i b i l i t y . ease in handling with hotcell manipulators.…”

Section: Tank Composite Sample Preparationmentioning

confidence: 98%

“…the t e s t i n g of 105-AN waste during f i s c a l year 1997 (Herting 1997) should be applicable t o t h e 104-AN waste. The t e s t s proposed here f o r t h e 104-AN waste a r e designed (1) t o v e r i f y t h e s i m i l a r i t y t o 105-AN waste in chemical and physical behavior, and ( 2 ) t o provide additional information on d i l u t i o n e f f e c t s .…”

Section: )mentioning

confidence: 99%

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Test plan for tank 241-AN-104 dilution studies

Herting¹

1998

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Approval ReasonIEl Title Key Words: d i l u t i o n , d i s s o l u t i o n , sodium s a l t s , p r i v a t i z a t i o n , v i t r i f i c a t i o n feed, r e t r i e v a l Abstract: t h e f i r s t tanks t o be r e t r i e v e d f o r low level waste pretreatment and immobilization. Retrieval o f the tank waste w i l l r e q u i r e d i l u t i o n . Laboratory tests a r e needed t o determine t h e amount and type of d i l u t i o nrequired f o r s a f e r e t r i e v a l and t r a n s f e r of feed and t o re-dissolve major soluble sodium s a l t s while not p r e c i p i t a t i n g out o t h e r s a l t s . The proposed laboratory t e s t s a r e described in t h i s document.Tank 241-AN-104 (104-AN) has been i d e n t i f i e d a s t h e one of TRADEMARK DISCLAIMER. Reference herein t o any specific comnercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply i t s endorsement, recomnendation, or favoring by the United States Government or any agency thereof or i t s contractors or subcontractors.

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Section: Tank Composite Sample Preparationmentioning

confidence: 98%

Section: )mentioning

confidence: 99%

Test plan for tank 241-AN-104 dilution studies

Herting¹

1998

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“…Data from Herting (1997) indicates that this dilution amount will dissolve the bulk of the soluble solids. The second transfer from AN-105 will be conducted after any remaining solids in the tank have been allowed to settle.…”

Section: Transfer Scenariosmentioning

confidence: 99%

“…Instrumentation errors are taken from Table 3.1. The waste data are taken or determined from Hedengren et al (2000), Herting (1997), Schreiber (1995), and Bingham et al (1999). Note that, in order to achieve the total transfer volume for Transfer 2 and 3, multiple transfers may be required for the vitrification plant tanks.…”

Section: Summary Of Input Datamentioning

confidence: 99%

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Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

Onishi¹,

Wells²,

Hartley³

et al. 2001

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SummaryPacific Northwest National Laboratory researchers developed a material balance assessment methodology based on conservation of mass to detect possible waste leaking and mis-routings during the pipeline transfer of double-shell tank waste with variable waste properties and tank conditions at Hanford. It is intended to be a backup method to pit leak detectors.The main factors causing variable waste properties and tank conditions are waste density changes caused by chemical reactions and gas generation/retention/release, the existence of a crust layer, and waste surface disturbance due to mixer pump operation during the waste transfer. If waste properties and tank conditions were constant, this mass-based material balance methodology could be simplified to a volume-based material balance.The material balance assessment methodology was applied to three waste transfers: AN-105 first transfer of 911,400 gallons of in-line diluted supernatant liquid; AN-105 second transfer with 673,000 gallons of liquid waste; and AZ-102 slurry transfer of 150,000 gallons. Three instrumentation setups were considered: (A) feed and receiver tank levels and diluent flow meter; (B) flow meter at the beginning of the transfer pipeline and receiver tank level; and (C) diluent, feed, and receiver tank levels.

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Review of the Scientific Understanding of Radioactive Waste at the U.S. DOE Hanford Site

Peterson¹,

Buck²,

Chun³

et al. 2018

Environ. Sci. Technol.

150

153

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This Critical Review reviews the origin and chemical and rheological complexity of radioactive waste at the U.S. Department of Energy Hanford Site. The waste, stored in underground tanks, was generated via three distinct processes over decades of plutonium extraction operations. Although close records were kept of original waste disposition, tank-to-tank transfers and conditions that impede equilibrium complicate our understanding of the chemistry, phase composition, and rheology of the waste. Tank waste slurries comprise particles and aggregates from nano to micro scales, with varying densities, morphologies, heterogeneous compositions, and complicated responses to flow regimes and process conditions. Further, remnant or changing radiation fields may affect the stability and rheology of the waste. These conditions pose challenges for transport through conduits or pipes to treatment plants for vitrification. Additionally, recalcitrant boehmite degrades glass quality and the high aluminum content must be reduced prior to vitrification for the manufacture of waste glass of acceptable durability. However, caustic leaching indicates that boehmite dissolves much more slowly than predicted given surface normalized rates. Existing empirical models based on ex situ experiments and observations generally only describe material balances and have not effectively predicted process performance. Recent advances in the areas of in situ microscopy, aberration-corrected transmission electron microscopy, theoretical modeling across scales, and experimental methods for probing the physics and chemistry at mineral-fluid and mineral-mineral interfaces are being implemented to build robustly predictive physics-based models.

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Results of dilution studies with waste from tank 241-AN-104

Abstract: Design Authority/ Date Cognzant Manager 21. DOE APPROVAL (if required) Ctrl No.

Cited by 27 publications

References 0 publications

Test plan for tank 241-AN-104 dilution studies

Test plan for tank 241-AN-104 dilution studies

Material Balance Assessment for Double-Shell Tank Waste Pipeline Transfer

Review of the Scientific Understanding of Radioactive Waste at the U.S. DOE Hanford Site

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