[en] This task addressed four items related to SuperLig(R) 644 ion exchange resin stability under nominal to extreme conditions

[en] Analytical data and plant solution compositions are often reported in molarity units. Densities of salt solutions are needed to convert the concentrations to molal basis in order to utilize physical property data that have been established on a molal basis, for example, solution reaction equilibrium constants or activity coefficients. We report here the densities at 20.0 Degrees C of sodium tetrafluoroborate (NaBF4) solutions from 0.05 molal to 9.0 molal, near saturation of 9.2 molal

[en] The Phase 2 portion of the HB-Line facility was built in the early 1980's to process plutonium and neptunium from nitric acid solutions into oxide suitable for storage in a vault. Although the other portions of HB-Line were started up in the mid 1980's and have operated since that time, the anion exchange and precipitation processes in Phase 2 were never started up. As part of the material stabilization efforts, Phase 2 is currently being started up. A new anion exchange resin is needed because the resins that were proposed for use 10 years ago are limited by performance characteristics, disposal requirements, or are no longer commercially available. SRTC is responsible for qualifying all resins prior to their use in Nuclear Materials Stabilization and Storage (NMSS) processes. Qualification consists of both process suitability and thermal stability with nitric acid. This report describes the thermal stability qualification of Reillextrademark HPQ, the new resin proposed for processing plutonium and neptunium in the HB Line facility

[en] Conditions were optimized for the first plant-scale dissolution of an aluminum-containing nuclear material without using mercury as a catalyst. This nuclear material was a homogeneous mixture of plutonium oxide and aluminum metal that had been compounded for use as the core matrix in Mark 42 nuclear fuel. Because this material had later failed plutonium distribution specifications, it was rejected for use in the fabrication of Mark 42 fuel tubes, and was stored at the Savannah River Site (SRS) awaiting disposition. This powder-like material was composed of a mixture of approximately 80 percent aluminum and 11 percent plutonium. Historically, aluminum-clad spent nuclear fuels [13] have been dissolved using a mercuric nitrate catalyst in a nitric acid (HNO3) solution to facilitate the dissolution of the bulk aluminum cladding. Developmental work at SRS indicated that the plutonium oxide/aluminum compounded matrix could be dissolved without mercury. Various mercury-free conditions were studied to evaluate the rate of dissolution of the Mark 42 compact material and to assess the corrosion rate to the stainless steel dissolver. The elimination of mercury from the dissolution process fit with waste minimization and industrial hygiene goals to reduce the use of mercury in the United States. The mercury-free dissolution technology was optimized for Mark 42 compact material in laboratory-scale tests, and successfully implemented at the plant

[en] The purpose of this work was to evaluate the reactivity of Reillex HPQ in 64 percent nitric acid and to address an accident scenario in which 64 percent nitric acid solution is inadvertently added to an HB-Line ion exchange column containing Reillex HPQ anion exchange resin

[en] This work simulates the inadvertent transfer of 1M sodium permanganate solution into the lead cesium ion exchange column containing SuperLig(R) 644 resin. The effects of contacting 1 molar sodium permanganate with SuperLig(R) 644 are characterized using the Advanced Reactive System Screening Tool

[en] The purpose of this work was to identify and quantify any flammable organic compounds remaining after digestion of Reillex (TM) HPQ anion exchange resin in potassium permanganate solution

[en] This work identifies and characterizes the low-temperature exothermic reaction of Reillex(TM) HPQ in nitric acid, investigates the origin of this reaction, and proposes a chemical pretreatment to eliminate it

[en] 'Existing plant flowsheets are insufficient for complete dissolution of unirradiated Mark 42 targets. One option being considered by Nuclear Materials Stabilization and Storage (NMSS) is to dissolve the aluminum components of the Mark 42 targets, allow plutonium solids to settle, transfer some of the aluminum-laden liquid out of the dissolver tank, and recharge the dissolver tank with fresh solution to achieve dissolution of the plutonium solids. The core problem associated with this two-step dissolution procedure is that, after the initial digestion of Mark 42 material, one to two micron-sized PuO2 particles settle from the mixture. Those particles are of concern because they may generate additional nuclear criticality safety requirements, and because they may be transferred out of the dissolver tank and disrupt the efficacy of downstream processes, such as solvent extraction. NMSS asked the Chemical Technology Group (CTG) to evaluate a decanting process in the presence of settled micron-sized particles using a one-fifth-scale mock-up of a canyon tank.'

[en] Despite reports of the relative inertness of Reillextrademark HPQ anion exchange resin to chemical and radiological degradation, a low temperature exothermic reaction was identified for this resin in nitric acid using the Reactive System Screening Tool (RSST). The purpose of this work is to characterize the low temperature exothermic reaction, investigate its origin, and evaluate the risks it introduces to plutonium processing at the Savannah River Site