EXECUTIVE SUMMARYA bank of four 2-cm centrifugal contactors was operated in countercurrent fashion to help address questions about organic carryover for the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). The contactors, having weirs sized for strip operation, were used to examine carryover for both strip effluent (SE) and decontaminated salt solution (DSS). Since only one bank of contactors was available in the short time frame of this work, the organic phase and only one aqueous phase were present in the flow loops at a time. Personnel maintained flowsheet-typical organic phase to aqueous phase (O:A) flow ratios when varying flow rates. Solvent from two different batches were tested with strip solution. In addition, potential mitigations of pH adjustment and coalescing media were examined.The experiment found that organic carryover after decanting averaged 220 ppm by mass with a range of 74 to 417 ppm of Isopar® L for strip effluent (SE)/organic solvent contacts. These values are based on measured modifier. Values were bounded by a value of 95 ppm based upon Isopar® L values as reported. The higher modifier-based numbers are considered more reliable at this time. Carryover of Isopar® L in DSS simulant averaged 77 ppm by mass with a range of 70 to 88 ppm of Isopar® L based on modifier content. The carryover was bounded by a value of 19 ppm based upon Isopar® L values as reported. More work is needed to resolve the discrepancy between modifier and Isopar® L values.The work did not detect organic droplets greater than 18 microns in SE. Strip output contained droplets down to 0.5 micron in size. Droplets in DSS were almost monodisperse by comparison, having a size range 4.7 +/-1.6 micron in one test and 5.2 +/-0.8 micron in the second demonstration. Optical microscopy provided qualitative results confirming the integrity of droplet size measurements in this work.Acidic or basic adjustments of aqueous strip solution from pH 3 to 1 and from pH 3 to 11 were not effective in clarifying the aqueous dispersions of organic droplets. Use of a 0.7-micron rated glass fiber filter of ¾ mm thickness under gravity flow provided significant reduction in organic content and increased clarity. A 2 inch element stack of "Teflon® Fiber Interceptor-Pak™" media from ACS Separations, Inc. was not effective in clarifying DSS simulant.

The Transuranic (TRU) Disposition Project at Savannah River Site will require numerous transfers of radioactive materials within the site boundaries for sorting and repackaging. The three DOT Type A shipping packagings planned for this work have numerous bolts for securing the lids to the body of the packagings. In an effort to reduce operator time to open and close the packages during onsite transfers, thus reducing personnel exposure and costs, an evaluation was performed to analyze the effects of reducing the number of bolts required to secure the lid to the packaging body. The evaluation showed the reduction to one-third of the original number of bolts had no effect on the packagings' capability to sustain vibratory loads, shipping loads, internal pressure loads, and the loads resulting from a 4-ft drop. However, the loads caused by the 4-ft drop are difficult to estimate and the study recommended each of the packages be dropped to show the actual effects on the package closure. Even with reduced bolting, the packagings were still required to meet the 49 CFR 178.350 performance criteria for Type A packaging. This paper will discuss the effects and results of the drop testing of the three packagings.

The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.

The 9977 / 9978 General Purpose Fissile Package (GPFP), has been designed as a cost-effective, user-friendly replacement for the DOT 6M Specification Package for transporting Plutonium and Uranium metals and oxides. To ensure the capability of the 9977 GPFP to withstand the regulatory crush test, urethane foam was chosen for the impact absorbing overpack. As part of the package development it was necessary to confirm that the urethane foam overpack would provide the required protection for the containment vessel during the thermal test portion of the Hypothetical Accident Conditions Sequential Tests. Development tests of early prototypes were performed, using a furnace. Based on the results of the development tests, detailed design enhancements were incorporated into the final design. Examples of the definitive 9977 design configuration were subjected to an all-engulfing pool fire test, as part of the HAC Sequential Tests, to support the application for certification. Testing has confirmed the package's ability to withstand the HAC thermal tests. INTRODUCTIONThe 9977 / 9978 GPFP has been designed as a replacement for DOT 6M Specification Packaging. As such, it must be able to transport the Plutonium and Uranium metals and oxides, meet the Type B performance requirements, and be economical to build and use. In order to enable the GPFP to withstand the Hypothetical Accident Condition (HAC) Crush Test, urethane foam was chosen for the impact absorbing overpack material. Finite element modeling (FEM) indicated that the rigid urethane foam-filled overpack employed by the GPFP design would be able to withstand the Crush Test.

New designs of radioactive material shipping packages are required to be evaluated in accordance with 10 CFR Part 71, Packaging and Transportation of Radioactive Material. This paper will discuss the use of digital radiography to evaluate the effects of the tests required by 10 CFR 71.71, Normal Conditions of Transport (NCT), and 10 CFR 71.73, Hypothetical Accident Conditions (HAC). One acceptable means of evaluating packaging performance is to subject packagings to the series of NCT and HAC tests. The evaluation includes a determination of the effect on the packaging by the conditions and tests. That determination has required that packagings be cut and sectioned to learn the actual effects on internal components.Digital radiography permits the examination of internal packaging components without sectioning a package. This allows a single package to be subjected to a series of tests. After each test, the package is digitally radiographed and the effects of particular tests evaluated. Radiography reduces the number of packages required for testing and also reduces labor and materials required to section and evaluate numerous packages. This paper will include a description of the digital radiography equipment used in the testing and evaluation of the 9977 and 9978 packages at SRNL. The equipment is capable of making a single radiograph of a full-sized package in one exposure. Radiographs will be compared to sectioned packages that show actual conditions compared to radiographic images.