Return side streams from anaerobic digesters and dewatering facilities at wastewater treatment plants (WWTPs) contribute a significant proportion of the total nitrogen load on a mainstream process. Similarly, significant phosphate loads are also recirculated in biological nutrient removal (BNR) wastewater treatment plants. Ion exchange using a new material, known by the name MesoLite, shows strong potential for the removal of ammonia from these side streams and an opportunity to concurrently reduce phosphate levels. A pilot plant was designed and operated for several months on an ammonia rich centrate from a dewatering centrifuge at the Oxley Creek WWTP, Brisbane, Australia. The system operated with a detention time in the order of one hour and was operated for between 12 and 24 hours prior to regeneration with a sodium rich solution. The same pilot plant was used to demonstrate removal of phosphate from an abattoir wastewater stream at similar flow rates. Using MesoLite materials, >90% reduction of ammonia was achieved in the centrate side stream. A full-scale process would reduce the total nitrogen load at the Oxley Creek WWTP by at least 18%. This reduction in nitrogen load consequently improves the TKN/COD ratio of the influent and enhances the nitrogen removal performance of the biological nutrient removal process.

A special thanks to Alex Nikolov and Darsh Wasan of the Illinois Institute of Technology for their expertise in foam and antifoamers, in helping us to develop the research program, to evaluate the results and to identify candidates for testing, and especially for introducing us to Kalman Koczo of Momentive Performance Materials who supplied us with the Momentive™ Y-17112. A special thanks to Gita Golcar for her identification of most of the antifoam candidates that we tested, including Evonik Surfynol ® MD20. We had great support from Meagan Kinard, Katherine Miles, Austin Coleman, and Daniel Jones in helping us to set up, develop R&D directions, perform the experiments, and so much more in finishing these tasks. Thanks to Mark Fowley and Andy Foreman for designing and installing the portable table that the RC1 equipment is assembled onto. Thanks to Christopher Verst for calculating radiation dose approximations and operating the J.L Shepherd Model 484 Co-60 gamma irradiator. Thanks to Mason Clark of DWPF Engineering for his support in the planning and execution of this testing. We had great support from our interns, Jackie Do from the University of Georgia and Maggie Hansen from Clemson University. Jackie and Maggie did a great job in helping prepare the equipment, procedures, R&D directions, and iControl software for the antifoam experiments.

Savannah River National Laboratory (SRNL) has been tasked with the radionuclide characterization of the washed Sludge Batch 10 (SB10) qualification sample. The washed SB10 qualification sample is based on SRR Engineering guidance and the sample slurry is expected to be similar in composition to Tank 51 slurry after final preparations for transfer to Tank 40.Forty-four radionuclides along with total alpha and beta activity have been reported herein. These radionuclide measurements are required for the Defense Waste Processing Facility (DWPF) Radiological Evaluation Program, DWPF Technical Safety Requirements (TSR)/Waste Acceptance Criteria (WAC) Evaluation, and the DWPF Solid Waste Characterization Program.

This report describes the results of testing performed to extend the applicable ranges of temperature and hydroxide concentration for use within the Glycolate and Global Total Organic Carbon (TOC) Hydrogen Generation Rate (HGR) expressions. Seven experimental conditions (six simulants of the 242-25H Evaporator system chosen as a D-optimal set of experiments and a single test conducted at an elevated boiling point of 170 °C) were investigated in the presence of sodium glycolate and Xiameter TM AFE-1010. Glycolate was employed to study the extension of the Glycolate Thermolytic HGR expression while Xiameter TM AFE-1010 was employed to study the extension of the Global TOC Thermolytic HGR expression. The following conclusions were derived from this testing.

The Next Generation Solvent (NGS) is set to replace the Original Caustic Side Solvent Extractant (CSSX) at the Salt Waste Processing Facility (SWPF).The Savannah River National Laboratory (SRNL) was requested by Savannah River Mission Completion (SRMC), formerly Savannah River Remediation (SRR), to perform a literature review on the following topics to address flammability concerns with the current solvent: Revision 0 Revision 0