The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants

McIsaac, C. V.; Mandler, J. W.

doi:10.2172/6417672

Title: The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants

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Abstract

Data are presented on the release of radionuclides, stable metals, and organic reagents from decontamination ion-exchange resin wastes solidified in Portland cement. Both solidified and unsolidified decontamination resin waste samples were collected from five commercial light water reactors following chemical decontaminations of primary coolant systems. The decontaminations were performed using the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of unsolidified decontamination resin waste were analyzed for concentrations of 10 CFR Part 61 radionuclides, selected transition metals, and organic chelating and complexing agents. The organic acids included oxalic acid, citric acid, formic acid, picolinic acid, ethylenediaminetetraacetic acid (EDTA), and diethylenetriaminepentaacetic acid (DPTA). Seven solidified resin waste samples were leached in deionized water following the ANS 16.1 leach-test procedure. Releases rates and leachability indexes of radionuclides, transition metals, and organic acids were determined. Analytical methods are described which were used to measure organic acids in resin wastes and in leachate solutions generated during leach-testing of waste form samples. Gas-liquid and ion chromatography methods were developed which allowed detection of organic acids in the tenths-of-a-ppM range. 59 refs., 65 figs., 55 tabs.

Authors:: McIsaac, C. V.; Mandler, J. W.

Publication Date:: Wed Mar 01 00:00:00 EST 1989

Research Org.:: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (United States)

OSTI Identifier:: 6417672

Report Number(s):: NUREG/CR-5224; EGG-2549
ON: TI89009371

DOE Contract Number:: AC07-76ID01570

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; LOW-LEVEL RADIOACTIVE WASTES; SOLIDIFICATION; PWR TYPE REACTORS; RESINS; LEACHING; CEMENTS; DATA ANALYSIS; DATA BASE MANAGEMENT; DECONTAMINATION; HYDRAULICS; ION EXCHANGE MATERIALS; RADIOISOTOPES; REACTOR SAFETY; WASTE MANAGEMENT; BUILDING MATERIALS; CLEANING; DISSOLUTION; FLUID MECHANICS; ISOTOPES; MANAGEMENT; MATERIALS; MECHANICS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; PETROCHEMICALS; PETROLEUM PRODUCTS; PHASE TRANSFORMATIONS; POLYMERS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTORS; SAFETY; SEPARATION PROCESSES; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 220900 - Nuclear Reactor Technology- Reactor Safety

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                    McIsaac, C. V., and Mandler, J. W. The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants.  United States: N. p., 1989. 
        Web.  doi:10.2172/6417672.

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                    McIsaac, C. V., & Mandler, J. W. The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants.  United States.  https://doi.org/10.2172/6417672

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                    McIsaac, C. V., and Mandler, J. W. 1989.  
        "The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants".  United States.  https://doi.org/10.2172/6417672.  https://www.osti.gov/servlets/purl/6417672.

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@article{osti_6417672,

  title        = {The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants},

  author       = {McIsaac, C. V. and Mandler, J. W.},

  abstractNote = {Data are presented on the release of radionuclides, stable metals, and organic reagents from decontamination ion-exchange resin wastes solidified in Portland cement. Both solidified and unsolidified decontamination resin waste samples were collected from five commercial light water reactors following chemical decontaminations of primary coolant systems. The decontaminations were performed using the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of unsolidified decontamination resin waste were analyzed for concentrations of 10 CFR Part 61 radionuclides, selected transition metals, and organic chelating and complexing agents. The organic acids included oxalic acid, citric acid, formic acid, picolinic acid, ethylenediaminetetraacetic acid (EDTA), and diethylenetriaminepentaacetic acid (DPTA). Seven solidified resin waste samples were leached in deionized water following the ANS 16.1 leach-test procedure. Releases rates and leachability indexes of radionuclides, transition metals, and organic acids were determined. Analytical methods are described which were used to measure organic acids in resin wastes and in leachate solutions generated during leach-testing of waste form samples. Gas-liquid and ion chromatography methods were developed which allowed detection of organic acids in the tenths-of-a-ppM range. 59 refs., 65 figs., 55 tabs.},

  doi          = {10.2172/6417672},

  url          = {https://www.osti.gov/biblio/6417672},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Wed Mar 01 00:00:00 EST 1989},

  month        = {Wed Mar 01 00:00:00 EST 1989}

}

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