Tank characterization data report: Tank 241-C-112

Simpson, B.C.; Borsheim, G.L.; Jensen, L.

doi:10.2172/10176393

Cited by 6 publications

(7 citation statements)

References 7 publications

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“…The material recovered from riser three was grayish white and did not appear to be ferrocyanide sludge. No water was measured in these samples, but large endothermic activity and substantial mass loss was noted at about 200 "C. The water and DSC results are reminiscent of the aluminum decladding waste found in tank 241-C-109 (Simpson et al 1993a), and the waste recovered from riser three is believed to be aluminum decladding waste.…”

Section: -9mentioning

confidence: 82%

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Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1994

Meacham¹,

Cash²,

Dukelow³

1994

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Section: -9mentioning

confidence: 82%

“…Simpson et al (1993aSimpson et al ( , 1993b. ** Vapor samples taken from in-tank, non-heated tubes using a vapor sampling cart (SUMMAm only -no NH3).…”

Section: -4mentioning

confidence: 99%

Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1994

Meacham¹,

Cash²,

Dukelow³

1994

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“…The met9 ions investigated were bismuth, lead, zinc, and chromium because analyses of samples from Tanks C-112 and C-109 showed these ions to be present in more than trace level concentrations (Simpson et al 1993a, b). The maximum average concentrations of chromium and zinc in acid-digested core composite analyses were 241 and 314 pg/g, respectively.…”

Section: Influence Of Bismuth Lead Zinc and Chromium Ions On If-1bmentioning

confidence: 99%

Ferrocyanide safety project ferrocyanide aging studies. Final report

Lilga¹,

Hallen²,

Alderson³

1996

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SummaryThis final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In Numerous studies conducted by the Task Team defmed safety criteria and resulted in closure of the USQ in March 1994. The potential for ferrocyanide reactions in Hanford Site SSTs was evaluated, and the energy released during these reactions was quantified. Dynamic X-ray diffraction was also used to identify specific reactions and to quantify reaction rates. In addition, a number of experimental and theoretical studies were conducted in an effort to analyze the thermal characteristics of the tanks and to investigate the likelihood of "hot spots" forming as a result of radiolytic heating.Resolving the Ferrocyanide Safety Issue requires that tank contents meet the safety criteria and operations be conducted such that waste conditions fall within the criteria limits. Because the ferrocyanide sludge has been exposed for many years to other highly caustic wastes, as well as to elevated temperatures and both gamma and beta radiation, ferrocyanide decomposition has occurred in the tanks. As a result, the concentration of ferrocyanide is less than that predicted by tank inventory records. As such, C-Farm tanks have been re-categorized as safe, allowing resolution of the Ferrocyanide Safety Issue for these tanks. In the PNNL studies, ferrocyanide waste simulants were used instead of actual waste. The simulants used in these studies were primarily In-Farm simulants, prepared by WHC to mimic the waste generated when the In-Farm flowsheet was used to remove radiocesium from waste supernates in the SSTs. In the In-Farm flowsheet, nickel ion and ferrocyanide anion were added to waste supernate to precipitate sodium nickel ferrocyanide and co-precipitate radiocesium. Once the radiocesium was removed, supernates were pumped from the tanks and disposed to the ground via cribs. Later, new wastes from cladding removal processes and/or from evaporators were added.These new wastes were typically highly caustic, having hydroxide ion concentrations of over 1 M and as high as 4 M. The Aging Studies investigated possible reactions between this caustic waste and the precipitated ferrocyanide waste in a radiation field.Over a 5-year period, these studies demonstrated and characterized the aging of ferrocyanide waste simulants through dissolution and hydrolysis processes. The experiments show the ultimate products are ammonia (which is slowly radiolyzed), carbonate, and oxides or hydroxides of iron and nickel. Thus, most of the fuel value in the solid phase is consumed in the process. Any ferrocyanide tank waste that contacted highly caustic waste also would undergo similar aging processes. The rate of agi...

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“…Low gas generation rates (Fowler and Graves 1994) and the low potential for exothermkferrocyanide reactions (Postma et al 1994a) indicated that continuous pressure monitoring is not warranted. I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Simpson et al (1993aSimpson et al ( , 1993b. 46 R. H. is the percent relative humidity calculated from measured dome space water content (mgk), temperature and atmospheric pressure.…”

Section: Pressure Monitoringmentioning

confidence: 99%