Material Recovery and Waste Form Development Strategic Plan
The Material Recovery and Waste Form Development Strategic Plan describes the strategy for the MRWFD Campaign in DOE NE-43.
Arm, Stuart T.↗
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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Materials Recovery and Waste Form Development -- Slides for Low Temperature Chlorination
These slides showcase the work done by INL in the low temperature chlorination work package during FY25.
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Sulfur Chloride Radiation Chemistry Activities
Presentation highlight the INL Center for Radiation Chemistry Research's contributions the Material Recovery & Waste Form Development Campaign on sulfur chloride processing technologies.
38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCL↗
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↗
Nuclear Fuel Cycle and Supply Chain (NFCSC) Technical Monthly October FY-20
The October FY20 Nuclear Fuel Cycle and Supply Chain (NFCSC) technical monthly report is provided. The usual topics are included: Advanced Fuels Campaign, Material Recovery and Waste Forms Development, MPACT Campaign, Systems Analysis and Integration Campaign, Joint Fuel Cycle Study Activities, and AFCI-HQ program Support.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Nuclear Fuel Cycle and Supply Chain (NFCSC) (Technical Monthly, March FY-20)
This report includes 1) Advanced Fuels Campaign, 2) Material Recovery and Waste Forms Development, 3) MPACT Campaign, 4) Systems Analysis and Integration (SA&I) Campaign), 5) Joint Fuel Cycle Study Activities, and 6) AFCI_HQ Program Support.
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Prioritizing Off-gas Metrics
Off-gas research within the Material Recovery and Waste Form Development (MRWFD) team is dispersed among four national laboratories and multiple universities and small businesses. Ensuring research is conducted consistently and in a manner conducive to direct comparison is a nontrivial task. The team assembled to realign goals and expectations by identifying distinct R&D phases, prioritizing crucial metrics, and outlining standardized tests specifically associated with Kr, Xe, and I capture.
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Study of Electrorefiner Sediment Re-Chlorination Options
A study was performed to investigate re-chlorination options for electrorefiner sediment, fulfilling a DOE Level 4 milestone within the Material Recovery and Waste Form Development campaign. The study stems from the recent identification of sediment that had accumulated in a kg-scale uranium electrorefiner at Idaho National Laboratory’s Hot Fuel Examination Facility. The study involved surveying, evaluating, and recommending options for re-chlorinating, or otherwise recovering, actinides from the sediment. Several options were investigated, including chemical and electrochemical techniques on the sediment within the electrorefiner (in situ approaches) or after its removal from the electrorefiner (ex situ approaches). A baseline approach was identified, involving electrolytic reduction of the removed sediment and subsequent electrorefining. Some options were dismissed for various deficiencies, while other options were recommended for further investigation.
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ORNL Production of Iodine Bearing Wasteforms
As part of the FY22 Material Recovery and Waste Form Development campaign, ORNL has prepared a new set of iodine-bearing sorbents.. Four canisters were machined and loaded with ~30 g each of iodine-bearing silver mordenite at varying degrees of sorbent saturation via hot isostatic pressing (HIP).
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Iodine Sorption on AgZ-PAN
The Department of Energy (DOE) Nuclear Fuel Cycle and Supply Chain Program Material Recovery and Waste Form Development (MRWFD) Campaign Off-gas Sigma Team has performed research and development on iodine control and iodine waste forms for the past several years. This research and development has included iodine adsorption tests using a laboratory-scale test system containing multiple-segmented fixed beds of iodine adsorbents. Iodine capture performance has been tested using (a) non-radioactive synthetic gas mixtures blended from air, nitrogen, NO, NO 2 , water, to simulate dissolver off-gas (DOG) and vessel off-gas (VOG) streams from used nuclear fuel aqueous reprocessing, (b) inorganic and organic iodine species, and (c) different sorbents. An initial test of silver-functionalized mordenite in polyacrylonitrile matrix (AgZ-PAN) was conducted to assess if this sorbent, initially designed for selective sorption of Xe that evolves into used fuel reprocessing off-gas streams, could also be a candidate for iodine sorption. This test was conducted using the same deep-bed test system and methodologies used in many prior iodine sorption tests using other sorbents. Diatomic iodine (I2) was used as the target iodide in a gas stream containing air, NO, NO 2 , and moisture designed to simulate an aqueous reprocessing dissolver off-gas (DOG) stream.
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A Brief Review of Technologies for Separating Tritium from the Aqueous Effluent of Reprocessing Plants
The scope of this letter report encompasses a review of technologies applicable to separating tritiated water from light and heavy water with a focus on wastewater arising from the reprocessing of UNF. Reports considering flowsheet options for tritium management are also reviewed. The main objective of this letter report is to support consideration of programmatic opportunities for the Materials Recovery and Waste Form Development (MRWFD) Campaign within the Department of Energy’s Office of Nuclear Energy.
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Organic Iodine Capture from Vessel Off-gas
The Department of Energy (DOE) Nuclear Fuel Cycle and Supply Chain Program Material Recovery and Waste Form Development (MRWFD) Campaign Off-gas Sigma Team has performed research and development on iodine control and iodine waste forms for the past several years. This research and development has included iodine adsorption tests using a laboratory-scale test system containing multiple-segmented fixed beds of iodine adsorbents. Iodine capture performance has been tested using non-radioactive synthetic gas mixtures blended from air, nitrogen, NO, NO2, water, and the target iodine compounds diatomic iodine (I2), representing likely inorganic iodides, and methyl iodide (iodomethane, CH3I) and 1-iodobutane (butyl iodide) a surrogates for potential organic iodides, that could exist in dissolver off-gas (DOG) and vessel off-gas (VOG) streams from used nuclear fuel aqueous reprocessing.
12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTE↗
Radiolytic Study of Single-Cycle Extraction Systems
Presentation for the Material Recovery and Waste Form Development Campaign Sprig Meeting (the afternoons of May 11-12) .
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Fundamental Radiation Chemistry
An overview presentation for the Fundamental Radiation Chemistry component of the Material Recovery and Waste Form Development campaign to be delivered to the campaign team. The overview includes all major findings from FY19 research projects, current state of FY20 research projects, additional projects completed between FY19 and now, and finally our vision for the future direction of the Fundamental Radiation Chemistry component.
38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCL↗
Off-Gas Design and Testing from Advanced Chlorination Process
Chlorination of Zr alloy cladding with sulfur-chloride reagents is being considered as a means of separating the main metal from alloying elements, imbedded U, actinides, and fission and activation products to purify the Zr. This would allow the Zr to be disposed of as low-level nuclear waste or possibly be recycled. A multistage process was developed that involves several steps and waste streams. Recycling of sulfur-chloride reagents S 2 Cl 2 and SOCl 2 is planned to minimize the waste stream. The generation of off-gas and entrainment of volatiles is anticipated to be minimized. However, given the complex nature of spent nuclear fuel (SNF), some volatile components will be generated, including the solvents themselves; Cl 2 used for the regeneration of S 2 Cl 2 ; volatile fission product chlorides, such as Sb and 3 H; and chlorinated alloying components, such as Sn, Nb, Fe, and Mo. This report discusses the chemical phenomena that might give rise to volatile species and their planned capture. The volatility of the transition metals will depend on their oxidation state and the compounds that are formed, such as Zr tritide. Loading radionuclides in the process off-gas will depend on the inputs to the process. For instance, processing separated Zr to reduce waste will have a much lower loading of radionuclides than if alternative chlorination were used for decladding SNF. Much of the volatile process streams will be part of the solvent recycling, which may involve online scrubbing. Generally, a caustic scrubber should be included in the off-gas to remove acidic vapors (e.g., Cl 2 , SOCl 2 ). The decontamination procedures for removing these species could involve pretreatment (i.e., heating) options or reduction by contact with H 2 . This report discusses these options along with a framework for testing these alternatives in future experiments. Technologies for off-gas capture will leverage those developed in the Materials Recovery and Waste Forms program.
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Aluminophosphate Waste Forms for Immobilizing Cations from Electrochemical Salt Wastes
This report provides experimental details and results of evaluating aluminophosphate waste forms for treating and immobilizing the salt cations from salt wastes generated during electrochemical reprocessing of used nuclear fuel. In the waste form process for these materials, chloride salt streams are reacted with NH 4 H 2 PO 4 , the chlorine is removed from the salts and driven off as NH 4 Cl (a solid condensate that can be captured), and then the product can be vitrified in conjunction with glass-forming chemicals (e.g., Fe 2 O 3 , Al 2 O 3 ) to create a high-durability waste form. This study was initiated with some literature review on aluminophosphates containing high alkali oxide content and some of this information is summarized in this report. Following literature review, three new samples were synthesized where two contained Fe 2 O 3 +Al 2 O 3 (i.e., samples G3 and G5 ) and one was only Al 2 O 3 (Fe 2 O 3 -free) (i.e., sample G6 ). In addition to these samples, G1 was also made, which is the baseline reference waste form referred to as DPF5-336 (made without Al 2 O 3 ). Samples G1, G3, G5, and G6 had phases of Li 3 Fe 2 (PO 4 ) 3 (likely), monazite (below XRD detection limits), AlPO 4 , and AlPO 4 , respectively. Characterizations on these materials included optical images, scanning electron microscopy, energy dispersive X-ray spectroscopy, and X-ray diffraction. These samples were shipped to Argonne National Laboratory for chemical durability testing. Depending on how the samples perform in these tests, an additional phase of aluminophosphate formulations could be designed and tested. This report completes the milestone M4FT-23PN030104041 with details provided in Appendix B.
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AFC Metal Fuel Workshop Presentations
Compilation of PowerPoint slide decks from presentations given at the 3rd Annual AFC Metal Fuels Workshop. The purpose of this workshop is to bring the national metallic fuel stakeholders together to discuss status and needs of metallic fuel and review the DOE AFC Metal Fuel R&D. Desired Outcomes - Advance Metallic Fuel Technology: 1. Stakeholder Community Building 2. National Program R&D Accountability, Planning Support, and Increased Stakeholder Advocation.
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Bosch Reactor Development for High Percentage Oxygen Recovery from Carbon Dioxide
This next Generation Life Support Project entails the development and demonstration of Bosch reaction technologies to improve oxygen recovery from metabolically generated oxygen and/or space environments. A primary focus was placed on alternate carbon formation reactor concepts to improve useful catalyst life for space vehicle applications, and make use of in situ catalyst resources for non-terrestrial surface missions. Current state-of-the-art oxygen recovery systems onboard the International Space Station are able to effectively recover approximately 45 percent of the oxygen consumed by humans and exhausted in the form of carbon dioxide (CO2). Excess CO2 is vented overboard and the oxygen contained in the molecules is lost. For long-duration missions beyond the reaches of Earth for resupply, it will be necessary to recover greater amounts of constituents such as oxygen that are necessary for sustaining life. Bosch technologies theoretically recover 100 percent of the oxygen from CO2, producing pure carbon as the sole waste product. Challenges with this technology revolve around the carbon product fouling catalyst materials, drastically limiting catalyst life. This project successfully demonstrated techniques to extend catalyst surface area exposure times to improve catalyst life for vehicle applications, and demonstrated the use of Martian and lunar regolith as viable catalyst Bosch Reactor Development for High Percentage Oxygen Recovery From Carbon Dioxide materials for surface missions. The Bosch process generates carbon nanotube formation within the regolith, which has been shown to improve mechanical properties of building materials. Production of bricks from post reaction regolith for building and radiation shielding applications were also explored.
Howard, David↗