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Fujimoto, Meghan S.

Publications and source records attributed to Fujimoto, Meghan S..

Solid Sorbent Cost Sensitivity Analysis: A Framework for UNF Reprocessing Sorbent Cost Comparison

Solid sorbents have been the subject of research and development across the U.S. Department of Energy national laboratory complex for many years. They are generally accepted as a safer alternative to cryogenic distillation for noble gas capture, and they present an easier pathway in development of long-term waste forms after iodine capture. As more types of sorbents have been proposed for capture of volatile radionuclides, it has become necessary to compare them based on performance and cost criteria. This report details cost and performance information for three promising sorbents and provides a cost sensitivity analysis. The goal of this analysis is to establish a framework which can be utilized to directly compare future sorbents, with differing properties, to the sorbents discussed in this report. Direct comparison is instrumental to making informed decisions to efficiently guide research and minimize laborious detours. In all cases, sorbent capacity is a major cost driver as it influences the mass of sorbent, operational footprint, and disposal cost requirements., However, sorbent price can greatly increase the cost of a capture technology. For sorbents used in krypton capture, the purity of krypton released to storage is the highest cost driver.

11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Integrated Off-gas System: A Preconceptual Design of an Integrated Off-Gas Treatment System

The U.S. has a vested interest in the advancement of nuclear energy to achieve aggressive net-zero goals, with reprocessing and recycling of used nuclear fuels (UNF) playing a vital role. It will not be possible to meet U.S. regulatory requirements without robust off-gas treatment, so it is crucial to advance treatment technologies to facilitate the design of future reprocessing facilities. For many years, teams of researchers across the U.S. Department of Energy (DOE) National Laboratory complex have been investigating off-gas treatment technologies for the capture and removal of volatile radionuclides (i.e., 85 Kr, Xe, 14 C, and 129 I) and oxides of nitrogen (NO X ) that are produced from reprocessing. These investigations have been focused on developing individual technologies for the capture of Kr, Xe, iodine, and CO 2 . Capture technologies for each constituent were tested independently from one another by utilizing nonradioactive surrogates to simulate simplified off-gas streams. The tests have been relatively small, laboratory-scale experiments of up to approximately 1 L/minute total gas flow rate. To increase the readiness of these technologies for deployment, an integrated test system with a larger-scale capacity is needed to bridge the gap between promising bench scale and fully scalable UNF reprocessing off-gas treatment. This document contains the goals, design basis, functional requirements, preconceptual design, and cost estimates for an integrated off-gas demonstration system for the capture and removal of NO x , Kr, Xe, CO 2 , and iodine at 10× higher throughput than earlier laboratory studies. The order-of-magnitude cost estimate for this system is approximately $\$$886,000. Next phases include conceptual design, detailed design, fabrication, and commissioning.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Xe Concentration Activity

INL conducted extensive studies to understand how the Xe capacity of AgZ-PAN changes under various conditions including flowrate, temperature, concentration, carrier gas, and irradiation of the sorbent. Therefore, it is well understood that AgZ-PAN can capture Xe under a wide range of conditions. While these studies were performed to prove that Xe can be completely desorbed from the column, the ability to concentrate Xe during desorption was not studied. Concentrating Xe during desorption would be ideal so as to produce Xe that can be used for commercial and research applications. This report investigates the Xe concentrating potential of AgZ-PAN by running multiple Xe adsorption-desorption cycles, collecting the desorbed effluent from a saturated AgZ-PAN column, and then loading it onto a fresh column.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Cost-Benefit Assessment of Krypton and Xenon Recovery from Aqueous Reprocessing

The purpose of this paper is to provide an understanding of the cost-benefit of capturing Kr and Xe from the existing process of aqueous reprocessing of UNF. The study accomplishes this with a market assessment of Xe prices and volumes today, coupled with a cost estimate of Kr and Xe capture out of cryogenic distillation within aqueous reprocessing. The market assessment shows that the average price of Xe is about $\$ $60/L while the average price of Kr is about $\$ $1/L. The assessment also shows that the market structure for Xe is one of oligopoly, in other words, very few suppliers to the Xe market. The assessment shows growing demand for Xe, particularly in medical applications like anesthesia. The cost assessment finds the unit cost of Xe to range from $\$ $71.50/L to $\$ $131.13/L. This range is only slightly above the current range of market prices today, and with growing demand for Xe, prices could reach the range it would take to support extraction of Xe from aqueous reprocessing. On the other hand, the estimated cost range for Kr is $\$ $830.15/L up to $\$ $1,522.52/L, which far exceeds the range of market prices for Kr. However, as the text notes, Kr capture is already part of aqueous reprocessing so these costs are sunk costs (already incurred) whereas the cost estimates for Xe are marginal cost (if Xe is desired, then the cost estimate would result from the Xe capture).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Prioritizing Off-Gas Metrics: A Guide for Comparable Off-Gas Capture Testing

The Material Recovery and Waste Form Development (MRWFD) off-gas team had a workshop, hosted by Idaho National Laboratory (INL), to align goals and expectations for off-gas research. The workshop included team members from four national laboratories. The workshop focused on defining distinct R&D phases with specific metrics, outlining standard test and measurement protocols for Iodine and Krypton/Xenon sorbents, brainstorming approaches to future disruptive technologies, and recognizing parameters with more inherent risk, requiring more rigorous evaluation. This report will serve as a guide for future off-gas work. Its purpose is to foster efficient collaboration across diverse research facilities and invite direct comparison of materials and results.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Demonstration of In Situ Down Blending During ZIRCEX Process

The Material Recovery Pilot Plant has successfully demonstrated in situ down-blending of HEU fuel to support INL’s commitment to HALEU production technologies. Depleted uranium pellets, along with an HEU fuel piece were placed in the hydrochlorinator and subsequently declad and oxidized. UOx product was recovered, analyzed, and demonstrated to have reduced enrichment within the targeted range of 20 – 30 % U-235. This first attempt at in situ down-blending will be followed by continued process refinement over the remaining fuel operations at MRPP.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Krypton Concentration using HZ-PAN

Idaho National Laboratory (INL) has developed and tested engineered sorbents to separate and capture volatile fission products such iodine, xenon (Xe), and krypton (Kr) from off-gas streams. As noble gases, Xe and Kr can be difficult to capture and separate. Historically, cryogenic distillation has been used to execute the separation. However, performing this separation from bulk air streams is expensive and can pose significant hazards. INL has successfully developed two different sorbents for Xe and Kr capture, silver mordenite polyacrylonitrile and hydrogen mordenite polyacrylonitrile (HZ-PAN). Adsorption studies to date successfully separated and captured Kr from carrier gas streams, but those studies focused primarily on initial separation and capture. Successful utilization in a used nuclear fuel (UNF) reprocessing facility, however, requires further concentration of the Kr to minimize long term storage volumes. This study focuses on the concentration of Kr utilizing HZ PAN as the concentrating media. Concentrating Kr during desorption is ideal for two reasons: one, to produce Kr that can be used for commercial and research applications, or two, to minimize the volume of the radioactive gaseous waste stream for disposal. This report investigates the Kr concentrating potential of HZ-PAN by running multiple Kr adsorption-desorption cycles, collecting the desorbed effluent from a saturated HZ-PAN column, and loading it onto a fresh column. This study demonstrates that four adsorption-desorption cycles can transform a 150 ppmv Kr stream into a 37.5% Kr stream, an overall concentration factor of 2497. Each concentration step results in successively smaller volumes desorbed, reducing volume by a factor of approximately 40,000. Depending on the operational goals, during desorption one could collect smaller volume fractions of high concentration Kr (~ 67%). This demonstration should be considered proof-of-concept. Further refinement is necessary to develop optimum operating schemes to integrate into UNF off-gas treatment.

12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTE↗

Effects of HZ-PAN Sorbent Irradiation on Kr Adsorption

Idaho National Laboratory (INL) has developed and studied an engineered form hydrogen mordenite in polyacrylonitrile matrix (HZ-PAN) for krypton (Kr) adsorption. Adsorption studies to date have successfully separated and captured Kr from carrier gas streams, but those studies have used non-radioactive gases for testing. However, if utilized in a used nuclear fuel (UNF) reprocessing facility, this sorbent will be exposed to the potential deleterious effects of radiation. This report explores Kr adsorption behavior on HZ PAN after the sorbent was exposed to gamma radiation. A batch of HZ-PAN was divided into five segments, a control segment that was not exposed to radiation, and the other four segments that were exposed to progressively increased levels of radiation dose, up to 5 MGy. Samples were then analyzed to determine total surface area as well as their capacity to capture Kr. This study reveals HZ PAN retains its initial surface area and Kr-capture capacity after radiation exposure, indicating viability for service in radioactive gases.

42 - ENGINEERING↗

Evaluation of Engineered Form MOFs CaSDB and HKUST-1

Idaho National Laboratory (INL) and Pacific Northwest National Laboratory (PNNL) have studied different sorbents for the purpose of separating krypton (Kr) and xenon (Xe). PNNL has researched various metal-organic frameworks (MOFs) that have characteristics theoretically suitable for the separation. Based on computational analysis, PNNL chose Calcium–4,4’–sulfonyl dibenzoate (CaSDB) and Hong Kong University of Science and Technology MOF1 (HKUST–1). The raw MOFs are supplied in a powder form and must be incorporated into a robust engineered form to be viable for gas separation. In 2016, PNNL produced an engineered form of CaSDB by compressing and grinding the raw MOF material. This form was sent to INL for adsorption testing. Gentle mechanical agitation of the compressed form produced a large amount of powder, resulting in the conclusion that the form was not viable for the application. In 2019, INL successfully produced two engineered forms, CaSDB–EF1 and HKUST–EF2, by incorporating the active MOF powders into a polyacrylonitrile (PAN) binder. PNNL also produced two engineered forms, CaSDB–10pmma and HKUST–10pmma, by using polymethyl methacrylate (PMMA) as a binder. Surface area analysis indicated that the forms could be viable for separations in which the CaSDB–EF1 retained 84% of the raw CaSDB surface area and CaSDB–10pmma retained 48%. HKUST–EF2 retained all the raw HKUST–1 surface area, whereas HKUST–10pmma retained only 28%. Mechanical stability testing demonstrated that the PMMA forms formed a fine powder whereas, the PAN forms did not. In general, adsorption testing showed that CaSDB–10pmma had a lower Xe breakthrough capacity than CaSDB–EF1, but a higher saturation capacity at both room temperature and at 253 K. The CaSDB MOF was intended to be used as a room temperature sorbent to capture Xe. However, both CaSDB engineered forms displayed relatively short initial break through times. Reduced temperature increased the Xe capacity of both engineered forms. HKUST–1 was expected to be effective only at sub-zero temperatures. At 195 K, HKUST–10pmma had an initial Xe breakthrough capacity of 119 mmol/ kg, compared to HKUST–EF2 at 339 mmol/ kg. The saturation capacities were 275 and 383 mmol/ kg, respectively. HKUST–10ppm also had a lower Kr capacity of 1.7 mmol/kg, whereas the HKUST–EF had a Kr capacity of 3 mmol/ kg. Test results indicate that the PAN engineered forms are a more suitable choice for the complete separation of Xe and Kr, due to the increase in initial breakthrough capacity. CaSDB allows rapid breakthrough of Kr and Xe regardless of the type of engineered form. At 253 K, it is more viable, but is still not the most effective sorbent. HKUST–EF2 demonstrated viability for Xe capture at 195 K, which may merit further study, however it may be cost prohibitive.

11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Probing the Radial Chemistry of Getter Components in Light Water Reactors via Controlled Electrochemical Dissolution

Getters are among the key functional components in the Tritium Producing Burnable Absorber Rods (TPBARs) of Light Water Reactors, and are used to capture the released tritium gas. They are cylindrical tubes comprised of the alloy zircaloy-4 which is coated with nickel plating both internally and externally. Their exposure to tritium as well as the irradiation environments in the light water reactors changes their structure, chemical composition and chemistry. Understanding the radial tritium distribution is key to gaining insight into the evolution of new chemistry upon irradiation in order to predict getter performance. Consequently, efforts are underway to devise a method that can allow selective probing into the getter core radially to probe the chemistry akin to carefully and selectively peeling of the layers of an onion. We have recently devised an electrochemical dissolution technique for controlled radial dissolution of zirconium based liners; this work describes the first proof-of-concept demonstration of the applicability of this technique on the controlled radial dissolution of nickel plated getters. The technique is complemented with periodic analysis of the electrolyte solution to measure the rates of release of the various elemental components and therefore glean information on their radial distribution across the getter; further complementary microscopy on the exposed surfaces allows us insight into the chemistry at the getter core.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Redox-Based Electrochemical Affinity Sensor for Detection of Aqueous Pertechnetate Anion

Rapid, selective, in-situ detection of TcO4- in multicomponent matrices consisting of interfering anions such as the ubiquitous NO3- and Cl- or the isostructural and isoelectronic CrO42- is challenging. Present sensors mostly lack the selectivity to exclude these interferences, or the sensitivity to meet the detection limits that are lower than the drinking water standards across the globe. This work presents an affinity based electrochemical sensor for TcO4- detection that relies on selective reductive precipitation of aqueous TcO4- induced by a capture probe immobilized on an electrode platform. This results in a direct decrease of the electron transfer current, the magnitude of the decrease being proportional to the amount of TcO4- added. Using this approach, we were able to achieve a detection limit of 1x10-10 M, which is lower than the drinking water standard of 5.2x10-10 M set by United States Environmental Protection Agency. Our proposed approach also allowed us to detect TcO4- from a multicomponent groundwater sample obtained from a well at the Hanford site in Washington (well 299-W19-36) that also contained NO3- , Cl- and CrO42-, without discernably affecting the detection limits.

Chatterjee, Sayandev↗

Evaluation of an Engineered Form MOF CaSDB

Under the Off-Gas Sigma Team, Idaho National Laboratory (INL) and Pacific Northwest National Laboratoory (PNNL) have been able to study various sorbents for the separation of krypton (Kr) and xenon (Xe). PNNL has researched and prepared various metal-organic frameworks (MOFs) to use for the separation. Calcium–4,4’–sulfonyl dibenzoate (CaSDB), a high surface area MOF, was synthesized and sent to INL for deep bed testing. The MOF showed an acceptable saturation capacity, but a low breakthrough capacity; However, the recieved MOF was deemed as unusable in a flow system because of its powdery nature. In 2018, PNNL sent a sample of CaSDB – MOF powder to INL with the goal to incorporate it into an engineered form that maintained adsorption properties comparable to the original MOF. It was anticipated that the engineered form of the sorbent would possess sufficient mechanical strength to be used in a column, and eliminate the dustiness of the raw material to improve handling and operability. An engineered from of CaSDB – MOF (CaSDB – EF1) was produced by incorporating the raw powder into a polyacrylonitrile (PAN) binder. The PAN binding material eliminated the dustiness of the raw MOF and provided a robust matrix that prevents damage from handling and use in a column. Xe adsorption testing of the sorbent revealed that it performs as well or better than previous CaSDB samples tested at INL, with an initial breakthrough capacity of 14.4 mmol/ kg at ambient temperature. Reducing the operating temperature to 253 K resulted in an increased breakthrough capacity of Xe.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Effect of Sulfate Sequestration by Ba-Sn Composite Material on Re Retention in Low-Activity Waste Glass

Difficulty incorporating radioactive Tc-99 into glass during vitrification of low-activity waste (LAW) at the Hanford Site is a technical challenge. Previous studies suggested that the presence of sulfate salts in the melt hinder the incorporation of Re, a non-radioactive surrogate for Tc-99, into nuclear waste glass. In this study, we assessed the capability of a Ba-Sn composite to sequester sulfate during vitrification of AN-102 LAW feed and the resulting effects on Re retention in the glass. We also investigated a feed where the initial soluble sulfate source in the simulated LAW (Na2SO4) was replaced with insoluble BaSO4. The Ba-Sn composite-treated feed and BaSO4-substitute feed were compared to a control, AN-102 baseline. The feeds were prepared and then heated to temperatures from 400-1000 °C at 5 °C/min and air-quenched to room temperature. The heated samples and dried feeds were leached in deionized water. The solutions from the leach test were analyzed by Inductively Coupled Plasma Optical Emission Spectroscopy (ICP-OES) to determine the amount of soluble sulfate as a function of temperature and the resulting solids were analyzed for Re retention. Although the Ba-Sn composite material successfully sequestered sulfate in the as-prepared LAW feed, heating to 400 °C resulted in most of the sulfate partitioning to a soluble salt phase. By 700°C, sulfate partitioning in the composite-treated feed was identical to the baseline feed. Throughout the entire temperature range the BaSO4-substitute feed behaved similarly to the composite-treated feed. The results of the study show that sequestering sulfate into a BaSO4 phase is ineffective for rhenium retention as the sulfate salt behavior was identical in the three feeds at =700 °C. The fraction of rhenium retained in the glass at 1000°C varied from 39.4-46.6% for the three feeds, which is shown to be an insignificant difference.

George, Jaime L.↗

Improving the sensitivity of electrochemical sensors through a complementary luminescent mode: A new spectroelectrochemical approach

Rapid and sensitive detection and quantification of trace and ultra-trace analytes is critical to environmental remediation, analytical chemistry and defense from chemical and biological contaminants. While affinity based electrochemical sensors have gained immense popularity, they occasionally are not able to meet the requirements of desired sensitivity and detection limits. Here, we demonstrate a complementary luminescence mode that can significantly enhance sensitivity of impedance or voltammetric electrochemical sensors. Our methodology involves using a redox probe, whose luminescence properties change upon changing the oxidation state. By tailoring the system such that these luminescence changes can be correlated with the capture of target analytes, we are able to significantly lower the detection limit and improve efficiency of detection compared to the electrochemical modes alone. Our proof-of-concept demonstration using a model system designed for Ca2+ capture, illustrated that the luminescent mode allowed us to lower the limits of detection by 3-orders of magnitude compared to the impedance or voltammetric modes alone without requiring any modification of electrode design or cell configuration.

environmental sensor, electrochemistry, affinity, ↗

Developing an Engineered Form of MOFs CaSDB and HKUST –1

Selective Kr and Xe capture to various adsorbents have been studied extensively as part of the Off-gas Sigma Team. In hopes to develop a better adsorbent, Pacific Northwest Nation Laboratory (PNNL) has suggested the use of metal-organic frameworks (MOFs). In 2016, PNNL developed compressed and ground engineered forms of calcium–4,4’–sulfonyl dibenzoate (CaSDB) MOF which was tested at Idaho National Laboratory (INL). The tests found that the CaSDB had a sufficient saturation capacity, but a low breakthrough capacity. The larger issue was that the CaSDB form was not robust enough to withstand handling necessary for installation in a column and flow system. In 2018, PNNL sent two MOFs, CaSDB and Hong Kong University of Science and Technology – 1 (HKUST–1), to INL. INL’s goal was to develop an engineered form that maintained adsorption properties comparable to the original MOFs and was robust enough to use in a column. Initial testing consisted of batch-wise contacts of the MOFs with aprotic solvents and water, to ensure there was not a dramatic degradation of the material. BET analyses confirmed that the MOFs could be exposed to water and DMSO without significant loses in surface area. MOF engineered forms were successfully produced, CaSDB–EF1 and HKUST–EF2, using the INL-patented PAN technique (USA Patent No. 8,686,083, 2013). Brunauer, Emmet and Teller (BET) analyses performed on the engineered forms yielded surface areas of 148 m 2 /g and 1487 m 2 /g for CaSDB–EF1 and HKUST–EF2 respectively, 67.6% and 83.7% of the surface areas of the respective pristine materials. Both engineered form MOFs are deemed acceptable for further study to determine efficacy for selective Kr and Xe capture.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Analysis of Uranium Ion Exchange Resin from the 200 West Pump-and-Treat Facility

The 200 West Area Pump-and-Treat (P&T) Facility at the Hanford Site is a multifunctional groundwater treatment facility consisting of unit processes to remove radionuclides such as uranium (U) and technetium (Tc-99) as well as other inorganic (nitrate and hexavalent chromium), and organic (carbon tetrachloride and trichloroethene) contaminants. The RAD building of the P&T Facility removes U and Tc-99 using ion exchange chromatography. In 2016, the Purolite A530E resin used for the Tc-99 removal was replaced and the spent resin was analyzed. In addition to Tc-99, the Purolite A530E resin also retained I-129 and Co-60; however, the resin loading was dominated by common groundwater constituents such as calcium, iron, silicon, and sulfate.

54 ENVIRONMENTAL SCIENCES↗

Inorganic Ba-Sn Nanocomposite Materials for Sulfate Sequestration from Complex Aqueous Solutions

Selective sequestration of sulfate (SO42-) in the form of barite (BaSO4) from alkaline solutions of high ionic strength containing carbonate at high concentrations resembling legacy radioactive waste generated during plutonium cold war era production is problematic due to the preferential formation of BaCO3. Incorporation of sulfate into the insoluble and thermally stable BaSO4 phase can potentially benefit radioactive waste processing in reducing operational challenges and suppressing volatilization of other waste components such as technetium-99. To enhance selectivity of SO42- sequestration, a series of Ba(II)-Sn(IV) materials was prepared using simple hydrothermal synthesis from different Sn(II) and Sn(IV) precursors. Structural characterization indicated that all obtained products predominantly contained BaSn(OH)6 and Ba2SnO2(OH)4(H2O)10 crystalline phases which were disrupted upon exposure to SO42- due to formation of BaSO4. Performance of the Ba(II)-Sn(IV) materials was tested using complex alkaline solutions simulating radioactive waste containing 0.094 M SO42- and 0.5 M CO32- among other constituents. About 54 – 66% of SO42- was converted to BaSO4 when a quantity of Ba(II)-Sn(IV) material containing approximately a stoichiometric amount of Ba2+ relative to SO42- was used. In comparison, previous studies indicate negligible BaSO4 formation under similar conditions when a simple Ba2+ salt is used. This improvement is attributed to the selective replacement of the Ba(II) stannate by SO42-. Thermal stability of the sulfate-loaded product material up to 1100 °C was demonstrated. Obtained materials offer a convenient and economical option for the selective sequestration or removal of SO42- from carbonate containing solutions.

Johnson, Isaac↗