testing at the end of the month. Due to these problems, operations with irradiated blankets are forecast for late July.

WBS 1.3 Metal Waste

Three batches (two assemblies each) of irradiated cladding from driver treatment operations will be converted into typical metal waste forms for waste qualification. Chemical analysis of the metal waste ingots shows good agreement with the predicted composition from cladding hull samples. The analysis of material phases has started.

WBS 1.4 Ceramic Waste Operation with Irradiated Materials

After 100 driver assemblies are treated in the Mk-IV electrorefiner, a portion of the salt will be transferred to the HFEF where the salt and fission products will be immobilized in ceramic waste samples. This activity is not scheduled to begin until February 1999.

WBS 1.5 Facility Operations

Two driver assemblies were received from the Radioactive Scrap and Waste Facility. At the end of the reporting period, 17 driver and 21 blanket assemblies (25 irradiated, 1 unirradiated) were stored in the FCF air cell. One unirradiated blanket assembly was transferred to the argon cell for initial start-up testing of the blanket equipment.

WBS 2.0 Equipment and Facility Modifications

This work element covers the engineering design, fabrication, assembly and testing activities that are required to implement new process equipment, equipment improvements or facility modifications that support operations or development activities.

The new, modified concentric ACM was shipped to Argonne-West. The V-mixer heaters were modified to correct the reliability problems that were identified during process qualifications. Since the V-mixer was not operational, the hot isostatic press (HIP) was transferred to the mock-up area for remote handling/operations qualification. After the remote qualification is completed, the HIP will process the materials from the V-mixer.

WBS 3.0 Treatment Process Development

The key step in electrometallurgical treatment of spent nuclear fuel is electrorefining to separate pure uranium from the spent fuel, thus reducing the volume of high level waste. Treatment of large quantities of spent fuel, such as the EBR-II blanket, required development of the high-throughput electrorefiner. The Mk-V high-throughput design known as the ACM has been installed in the FCF at ANL-W for demonstration operations with the EBR-II blanket fuel. One of the Mk-V ACMs was prepared for testing at ANL-E, in the J-118 laboratory. Testing of the unit outside the glovebox was done to check for proper fit-up and operation. Fabrication and/or modifications were completed on all of the components needed for testing the Mk-V ACM in the glovebox. Some minor fabrication errors were detected and corrected, and initial shake-down testing and operations are expected to begin in June.

WBS 4.0 Process Modeling and Analysis

These activities develop and apply models to improve the understanding of various process steps; to help in design of equipment and selection of process variables; to evaluate the data on performance of the engineering-scale equipment; to provide support in planning of test campaigns; and to conduct operations.

The anode-cathode modeling status report, which was a DOE milestone, was issued in May 1998. This report describes the computational fluid dynamics analysis that is assisting in the understanding of the new high throughout electrorefiner.

WBS 5.0 Metal Waste Treatment Development

The noble metal fission products and undissolved cladding hulls are immobilized into a stainless steel-zirconium alloy for geologic repository disposal. In support of waste qualification activities, small samples of the metal waste are being produced so they can be characterized to establish the performance. Also,



The National Academies | 500 Fifth St. N.W. | Washington, D.C. 20001
Copyright © National Academy of Sciences. All rights reserved.
Terms of Use and Privacy Statement