STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING

HOBBS, D. T. ; BARNES, M. J. ; PULMANO, R. L. ; MARSHALL, K. M. ; EDWARDS, T. B. ; BRONIKOWSKI, M. G. ; FINK, S. D.

Savannah River Site (S.C.)

关键词: Removal;    Reprocessing;    Testing;    Plutonium Isotopes;    Liquid Wastes;   

DOI  :  10.2172/881358
RP-ID  :  WSRC-MS-2005-00266
RP-ID  :  DE-AC09-96SR18500
RP-ID  :  881358

美国|英语

来源: UNT Digital Library

【 摘 要 】

High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and ion exchange/sorption of {sup 90}Sr and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition and the oxidation state of plutonium.