Removal of mercury from waste water: Large scale performance of an ion exchange process

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The Integrated Defense Waste Processing Facility (DWPF) Melter System (IDMS), located at the Savannah River Site (SRS), provides an engineering scale, non-radioactive demonstration of the DWPF. The DWPF will soon be used to immobilize high level radioactive waste (HLW) in borosilicate glass. Part of the IDMS charter is to demonstrate the removal of mercury from simulated HLW on an engineering-scale. An ion exchange facility (IEF), utilizing Duolite{trademark} GT-73 ion exchange resin, was designed to treat the mercury laden waste water (condensate and sump water). The IEF became operational in January of 1990 and routinely reduces the mercury content of the ... continued below

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Pages: (18 p)

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Ritter, J.A. & Bibler, J.P. January 1, 1990.

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Description

The Integrated Defense Waste Processing Facility (DWPF) Melter System (IDMS), located at the Savannah River Site (SRS), provides an engineering scale, non-radioactive demonstration of the DWPF. The DWPF will soon be used to immobilize high level radioactive waste (HLW) in borosilicate glass. Part of the IDMS charter is to demonstrate the removal of mercury from simulated HLW on an engineering-scale. An ion exchange facility (IEF), utilizing Duolite{trademark} GT-73 ion exchange resin, was designed to treat the mercury laden waste water (condensate and sump water). The IEF became operational in January of 1990 and routinely reduces the mercury content of the waste water from a feed concentration ranging from 0.2 to 70 ppm (mg/l) down to an effluent concentration ranging from 1 to 5 ppb. However, two operational problems have been encountered: (1) the stated capacity of the resin for mercury was not being achieved, and (2) the IEF was temporarily shut down because the mercury content of the waste water could not be reduced to below the permitted level, even with fresh resin. The primary purpose of this paper is to present some specific details on these two problems along with general information on the process characteristics and performance. A secondary purpose is to advocate the use of Duolite{trademark} GT-73 ion exchange resin as it has proven to be a reliable means to remove mercury and other heavy metals from SRS waste water streams which vary considerably in composition.

Physical Description

Pages: (18 p)

Notes

OSTI; NTIS; GPO Dep.

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  • 2. international conference on waste management in the chemical and petrochemical industries: toxics management, New Orleans, LA (United States), 17-20 Jun 1991

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  • Other: DE92009599
  • Report No.: WSRC-MS-90-288
  • Report No.: CONF-910698--2
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 5671841
  • Archival Resource Key: ark:/67531/metadc1093282

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 1990

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  • Feb. 10, 2018, 10:06 p.m.

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  • May 15, 2018, 4:32 p.m.

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Ritter, J.A. & Bibler, J.P. Removal of mercury from waste water: Large scale performance of an ion exchange process, article, January 1, 1990; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc1093282/: accessed July 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.