Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste

Metcalfe, Brian L; Donald, Ian W; Fong, Shirley K; Gerrard, Lee A; Strachan, Denis M; Scheele, Randall D

doi:10.1016/j.jnucmat.2008.12.035

Title: Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste

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Abstract

AWE has developed a process for the immobilization of ILW waste containing a significant quantity of chloride using Ca3(PO4)2 as the host material. Waste ions are incorporated into two phosphate based phases, chlorapatite, Ca5(PO4)3Cl, and spodiosite, Ca2(PO4)Cl. Non-active trials performed at AWE using samarium as the actinide surrogate demonstrated the durability of these phases in aqueous solution. Trials of the process using actinide-doped material were performed at PNNL which confirmed the immobilized wasteform resistant to aqueous leaching. Initial leach trials conducted on 239Pu /241Am loaded ceramic at 40°C/28 days gave normalized mass losses of 1.2 x 10-5 g.m-2 and 2.7 x 10-3 g.m-2 for Pu and Cl respectively. In order to assess the response of the phases to radiation-induced damage, accelerated ageing trials were performed on samples in which the 239Pu was replaced by 238Pu. No changes to the crystalline structure of the waste were detected using XRD after the samples had experienced a radiation dose of 4 x 1018 α.g-1. Leach trials showed that there had been an increase in the P and Ca release rates but no change in the Pu release rate.

Authors:: Metcalfe, Brian L; Donald, Ian W; Fong, Shirley K; Gerrard, Lee A; Strachan, Denis M; Scheele, Randall D

Publication Date:: Tue Mar 31 00:00:00 EDT 2009

Research Org.:: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 977322

Report Number(s):: PNNL-SA-60313
830403000

DOE Contract Number:: AC05-76RL01830

Resource Type:: Journal Article

Journal Name:: Journal of Nuclear Materials, 385(2):485-488

Additional Journal Information:: Journal Name: Journal of Nuclear Materials, 385(2):485-488

Country of Publication:: United States

Language:: English

Subject:: actinide waste disposal, immobilization, ceramic immobilization

Citation Formats


                    Metcalfe, Brian L, Donald, Ian W, Fong, Shirley K, Gerrard, Lee A, Strachan, Denis M, and Scheele, Randall D. Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste.  United States: N. p., 2009. 
        Web.  doi:10.1016/j.jnucmat.2008.12.035.

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                    Metcalfe, Brian L, Donald, Ian W, Fong, Shirley K, Gerrard, Lee A, Strachan, Denis M, & Scheele, Randall D. Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste.  United States.  https://doi.org/10.1016/j.jnucmat.2008.12.035

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                    Metcalfe, Brian L, Donald, Ian W, Fong, Shirley K, Gerrard, Lee A, Strachan, Denis M, and Scheele, Randall D. 2009.  
        "Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste".  United States.  https://doi.org/10.1016/j.jnucmat.2008.12.035.

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@article{osti_977322,

  title        = {Ageing of a phosphate ceramic used to immobilize chloride contaminated actinide waste},

  author       = {Metcalfe, Brian L and Donald, Ian W and Fong, Shirley K and Gerrard, Lee A and Strachan, Denis M and Scheele, Randall D},

  abstractNote = {AWE has developed a process for the immobilization of ILW waste containing a significant quantity of chloride using Ca3(PO4)2 as the host material. Waste ions are incorporated into two phosphate based phases, chlorapatite, Ca5(PO4)3Cl, and spodiosite, Ca2(PO4)Cl. Non-active trials performed at AWE using samarium as the actinide surrogate demonstrated the durability of these phases in aqueous solution. Trials of the process using actinide-doped material were performed at PNNL which confirmed the immobilized wasteform resistant to aqueous leaching. Initial leach trials conducted on 239Pu /241Am loaded ceramic at 40°C/28 days gave normalized mass losses of 1.2 x 10-5 g.m-2 and 2.7 x 10-3 g.m-2 for Pu and Cl respectively. In order to assess the response of the phases to radiation-induced damage, accelerated ageing trials were performed on samples in which the 239Pu was replaced by 238Pu. No changes to the crystalline structure of the waste were detected using XRD after the samples had experienced a radiation dose of 4 x 1018 α.g-1. Leach trials showed that there had been an increase in the P and Ca release rates but no change in the Pu release rate.},

  doi          = {10.1016/j.jnucmat.2008.12.035},

  url          = {https://www.osti.gov/biblio/977322},
  journal      = {Journal of Nuclear Materials, 385(2):485-488},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Mar 31 00:00:00 EDT 2009},

  month        = {Tue Mar 31 00:00:00 EDT 2009}

}

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