Radionuclide Retention in Concrete Waste Forms

Mattigod, Shas V. ; Bovaird, Chase C. ; Wellman, Dawn M. ; Wood, Marcus I.

关键词: AR FACILITIES;    AGING;    CEMENTS;    CONCRETES;    ELECTRIC GROUNDS;    GROUTING;    INTERACTIONS;    MATERIALS;    PRECIPITATION;    RADIOISOTOPES;    RADIONUCLIDE MIGRATION;    RANGE;    RETENTION;    SOLIDS;    SOLUBI;   

DOI  :  10.2172/1001511
RP-ID  :  PNNL-19823
PID  :  OSTI ID: 1001511
Others  :  Other: 830403000
Others  :  TRN: US1100792

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how waste form performance is affected by the full range of environmental conditions within the disposal facility; the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of waste form aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. The information presented in the report provides data that 1) quantify radionuclide retention within concrete waste form materials similar to those used to encapsulate waste in the Low-Level Waste Burial Grounds (LLBG); 2) measure the effect of concrete waste form properties likely to influence radionuclide migration; and 3) quantify the stability of uranium-bearing solid phases of limited solubility in concrete.