Task Technical and Quality Assurance Plan for Determining Uranium and Plutonium Solubility in Actual Tank Waste Supernates

King, William D.

Savannah River Site (S.C.)

关键词: Uranium;    Radioactive Waste Storage;    Liquid Wastes;    Chemical Composition;    Solubility;   

DOI  :  10.2172/881501
RP-ID  :  WSRC-RP-2005-01625
RP-ID  :  DE-AC09-96SR18500
RP-ID  :  881501

美国|英语

来源: UNT Digital Library

【 摘 要 】

Savannah River Site tank waste supernates contain small quantities of dissolved uranium and plutonium. Due to the large volume of supernates, significant quantities of dissolved uranium and plutonium are managed as part of waste transfers, evaporation and pretreatment at the Savannah River Site in tank farm operations, the Actinide Removal Project (ARP), and the Salt Waste Processing Facility (SWPF). Previous SRNL studies have investigated the effect of temperature and major supernate components on the solubility of uranium and plutonium. Based on these studies, equations were developed for the prediction of U and Pu solubility in tank waste supernates. The majority of the previous tests were conducted with simulated waste solutions. The current testing is intended to determine solubility in actual tank waste samples (as-received, diluted, and combinations of tank samples) as a function of composition and temperature. Results will be used to validate and build on the existing solubility equations.