Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste

Caustic Recycle from Hanford Tank Waste Using Large Area NaSICON Structures (LANS)

“…A 1.5L tank-waste sample previously treated by ion exchange was located and deemed as representative tank-waste feed for conducting caustic recycle experiments. Table 2.1 and Table 2.2 identify the estimated constituent and radionuclide concentrations, respectively, and are based on analysis of samples obtained after cesium ion-exchange treatment (Fiskum et al 2009). Details of the tank waste sample origin and processing are provided elsewhere (Fiskum et al 2008, Fiskum et al 2009).…”

“…Table 2.1 and Table 2.2 identify the estimated constituent and radionuclide concentrations, respectively, and are based on analysis of samples obtained after cesium ion-exchange treatment (Fiskum et al 2009). Details of the tank waste sample origin and processing are provided elsewhere (Fiskum et al 2008, Fiskum et al 2009). For purposes of reference in this report the composited Group 5 and 6 Cs-depleted supernatant tank waste will be referred to as "Group 5 and 6 tank waste."…”

Functions and Requirements of the Radioactive Waste Test Platform

“…The purpose of this document is to provide the function and requirements for the Radioactive Waste Test Platform (hereafter called "test platform"). Historically, testing has been performed at the bench scale with actual waste samples (Fiskum et al 2006a(Fiskum et al , b, 2008(Fiskum et al , 2009Lumetta et al 2009;Edwards et al 2009;Smith et al 2000Smith et al , 2001. These tests form the basis for waste treatment operations at the Hanford Site.…”

Evaluations of Mechanisms for Pu Uptake and Retention within Spherical Resorcinol-Formaldehyde Resin Columns

“…Both PNNL (Fiskum et al 2009) and SRNL (Nash and Duignan 2010) have undertaken comprehensive ion-exchange column tests to determine the performance of spherical resorcinol-formaldehyde (sRF) resin in removing radioactive Cs (largely present as 137 Cs) from actual alkaline waste solutions from the Hanford Site and from the Savannah River Site (SRS), respectively. The sRF beads, in the hydrogen ion (H + ) form shown in Figure 1, are highly uniform in shape and diameter.…”

“…The U concentrations did not correlate with any of the anion concentrations. 1.94×10 -8 1.35×10 -8 5.86×10 -9 3.29×10 -8 U 1.53×10 -5 1.93×10 -5 5.21×10 -6 1.79×10 -4 3.39×10 -5 Reference (Fiskum et al 2009) a (Nash and Duignan 2010) b (Hassan and Adu-Wusu 2003) c (Fiskum et al 2006a) d (Fiskum et al 2006c) e a -From Tables 5.10 and 5.11 of Fiskum et al (2009). Pu concentrations for tests with Hanford wastes are based on 239,240 Pu analyses and the Pu isotopic composition of 0.021 wt% 238 Pu, 93.9 wt% 239 Pu, 5.86 wt% 240 Pu, 0.163 wt% 241 Pu, and 0.044 wt% 242 Pu derived by decay-correction to 1 July 2008 from best-basis tank-waste inventories found in Table ES-2 of Kupfer et al (1999).…”