Equilibrium data for cesium ion exchange of Hanford CC and NCAW tank waste

Abstract

Reprint of hirtorical document TWRSPP-sZ-020. dated 1992. Data. formatting, and Mher mmntionr reflect stardards at the origiml date of printing. Tcchnieal peer reviews and editorial reviews may r a have teen performed. Laboratory (PNL) has studied several ion exchange materials f o r the recovery of cesium from Hanford waste tanks. tasks, 1) t o obtain equilibrium data f o r cesium ion exchange, and 2) t o evaluate ion exchange column performance. The subject of this l e t t e r report ' is the measurement of batch distribution coefficients f o r several ion exchange medi,a f o r a range of operating conditions f o r two types of waste; complexant concentrate (CC) and neutralized current acid waste (NCAW) DISCLAIMERThe WHC program was divided into two main . Equilibrium data was obtained f o r the ion exchange materials IONSIV IE-96 (a zeolite produced by UOP), CS-100 (an organic resin produced by Rohm and ' Haas) and SRL-DJ (a new resorcinol-formaldehyde organic resin produced by Boulder Scientific). coefficients (Cs Kd) were obtained a t temperatures of 10°c, 25OC and 4OoC using simulated NCAW and CC wastes. Results obtained f o r the SRL-DJ exchanger were inconsistent -w i t h previous PNL results w i t h material sent from the Savannah River Laboratory (SRL). Dr. Jane Bibler (SRL) provided new material from a 50 lb l o t that was prepared by Boulder Scientific (BIB-DJj. Excellent results were obtained using the BIB-DJ resin. The following conclusions were developed a f t e r completion of the batch distribution study:Five hundred (500) cesium batch distributionThe cesium ion exchange capacity of IE-96 and CS-100 doubles as the temperature is varied from 4OoC t o 10°C. effect was not as pronounced f o r the BIB-DJ resin. The i n i t i a l volume of feed that can be processed using IE-96 inlreases w 50% w i t h a 3X feed dilution (6M Na d i l u t e d t o 2M Na ). The i n i t i a l feed volume w i t h the BIB-DJ resin decreases by ~1 0 % w i t h a 3X feed dilution, and >30% w i t h CS-100.The x values (A = cs Kd x pb) f o r cesium ion exchange a t 5~ Na' f o r NCAW and CC waste were similar; 45-57, 65-80 and 240 f o r CS-100, IE-96,4and BIB-DJ, respectively, a t an equilibrium Na/Cs mole r a t i o of 10 , a t 10°C. From these results, i t is postulated that basic ion exchange data can be applied t o a broad range of tank waste types.The temperature i i i . 4... Potassium (K' ) was found t o exert an effect on X , over a Na/K range of 11 t o 200. An increa3ing amount of K was found t o decrease the cesium X as the K competes w i t h the-cesium for ion exchange s i t e s .Rubidium was found t o have a negligible effect on X over a Na/Rb range of 1.15E4 -4.6E4 (Cs/Rb = 0.2 t o 92). While rubidium can be expected t o compete w i t h the cesium for ion exchange s i t e s , the Cs/Rb ratios tested were not small enough t o be significant.....

Performance evaluation of 24 ion exchange materials for removing cesium and strontium from actual and simulated N-Reactor storage basin water

“…This is a subset of the results displayed in Figure 3.1 and represents a range of data which are readily visible on the graph. The data profile is similar to that observed previously for cesium removal by ion exchange batch distribution tests from simulated and actual tank wastes (Bray et al 1992;Bray et al 1993a;Brown et al 199%;Brown et al 1996b;Kurath et al 1994). In general, for every material, the cesium K,, is nearly constant at low cesium concentration (e.g., less than 1 .OE-06 M Cs) but decreases at higher concentration (e.g., greater than 1.0505 M Cs).…”

“…CS-100 and resorcinol-formaldehyde (R-F) are two organic ion exchange resins that are commercially available and under consideration for cesium removal from Hanford tank wastes (Eager et al 1994;Kurath et al 1994;Orme 1995;Penwell et al 1994;Gallagher 1986@) CO), has been shown to exhibit a much greater loading for cesium and selectivity over sodium or potassium than the CS-100 resin (Bibler et al 1989;Bibler 1994;Bray et al 1990;Bray et al 1992;Bray et al 1993a;Brown et al 1995b;Kurath et al 1994). The chemical and radiation stability (Bibler 1991;Bibler and Crawford 1994;Brown et al 199%;Carlson et al 1995) and the structwe/function relationship (Hubler et al 1995;Hubler et al 1996a;Hubler et al 1996b) of the R-F resin to the ion exchange process have been studied extensively.…”

Radiation testing of organic ion exchange resins

“…Experimental work completed from Fy 1992 through FY 1993 for cesium recovery included the determination of cesium batch distribution coefficients for three exchangers and two waste types (Bray et al 1992). the initiation of ion exchange column studies (Bray et al 1993), and radiation stability studies of the phenol formaldehyde resin CS-100 using 6OCo gamma irradiation (Bryan et al 1993).…”

“…Complexant concentrate (CC) and NCAW were selected for the initid investigation (Bray et al 1992). Organic CC waste represents a high sodium waste containing organic complexants.…”

Assessment of commercially available ion exchange materials for cesium removal from highly alkaline wastes

“…The memos from Prignano (1989a and b) provided batch distribution information in NCAW and HN03 elution with Duolite CS-100, resorcinol formaldehyde (R-F), Duolite C-3, and ARC-359N in NCAW simulant. More recent work has focused on cesium sorption with IE-96, R-F, and CS-100 resins (Bray, et al 1992;Kurath et al 1994). Marsh, et al (1994a) has recently completed a comparison of resins in 101-SY simulant with CS-100, R-F, Ionsiv TIE-96 (IE-96 with titanium to improve Pu and Sr sorption), Durasil 230, and several other exchangers.…”