I-NERI-2007-004-K, DEVELOPMENT AND CHARACTERIZATION OF NEW HIGH-LEVEL WASTE FORMS FOR ACHIEVING WASTE MINIMIZATION FROM PYROPROCESSING

S.M. Frank

关键词: AR FACILITIES;    ACTINIDES;    CERAMICS;    CHLORIDES;    FABRICATION;    FISSION PRODUCTS;    HALIDES;    HOT CELLS;    IDAHO NATIONAL LABORATORY;    KAERI;    LEACHING;    MINIMIZATION;    NUCLEAR ENERGY;    NUCLEAR FUELS;    OXIDES;    RADIOACTIVITY;    SAMPLE PREPARATION;    SCANNING ELECTRON MICROSCOPY;    WASTE FORMS;    WASTE MANAGEMENT;    WASTES;    X-RAY DIFFRACTION Advanced waste forms;   

DOI  :  10.2172/1033888
RP-ID  :  INL/EXT-11-23352
PID  :  OSTI ID: 1033888
Others  :  TRN: US1200669

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

Work describe in this report represents the final year activities for the 3-year International Nuclear Energy Research Initiative (I-NERI) project: Development and Characterization of New High-Level Waste Forms for Achieving Waste Minimization from Pyroprocessing. Used electrorefiner salt that contained actinide chlorides and was highly loaded with surrogate fission products was processed into three candidate waste forms. The first waste form, a high-loaded ceramic waste form is a variant to the CWF produced during the treatment of Experimental Breeder Reactor-II used fuel at the Idaho National Laboratory (INL). The two other waste forms were developed by researchers at the Korean Atomic Energy Research Institute (KAERI). These materials are based on a silica-alumina-phosphate matrix and a zinc/titanium oxide matrix. The proposed waste forms, and the processes to fabricate them, were designed to immobilize spent electrorefiner chloride salts containing alkali, alkaline earth, lanthanide, and halide fission products that accumulate in the salt during the processing of used nuclear fuel. This aspect of the I-NERI project was to demonstrate 'hot cell' fabrication and characterization of the proposed waste forms. The outline of the report includes the processing of the spent electrorefiner salt and the fabrication of each of the three waste forms. Also described is the characterization of the waste forms, and chemical durability testing of the material. While waste form fabrication and sample preparation for characterization must be accomplished in a radiological hot cell facility due to hazardous radioactivity levels, smaller quantities of each waste form were removed from the hot cell to perform various analyses. Characterization included density measurement, elemental analysis, x-ray diffraction, scanning electron microscopy and the Product Consistency Test, which is a leaching method to measure chemical durability. Favorable results from this demonstration project will provide additional options for fission product immobilization and waste management associated the electrochemical/pyrometallurgical processing of used nuclear fuel.