Search NASA⌕ Search

SEARCH · Search NASA

Results for “Waste Transfer”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 1,369 records · Page 76
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Transition of Site Programs and Implementation of Decommissioning Agent Oversight - 18653

San Onofre Nuclear Generating Station (SONGS), acting as the Decommissioning Agent (DA), retained its NRC License and contracted a Decommissioning General Contractor (DGC) to manage plant programs and execute the Demolition and Dismantlement (D and D) of the site. To support this effort, over twenty-one programs transitioned to the DGC, including Occupational Health and Safety, Radiation Protection, Maintenance, and Engineering. In addition, SONGS effected a cultural shift from an operating station performing work to one of overseeing it. The framework and road map for this kind of D and D model is new to the industry. This presentation shares the SONGS' experience and lessons learned associated with this transition. SONGS and the DGC entered an Agreement that established the contractual requirements and responsibilities of the parties, the Scope of Work, and the mechanisms to ensure effective transition of DA programs. As a part of defining the Scope of Work, the contract established functional areas and divisions of responsibilities divided into the roles of Governance, Oversight, Support, and Performance (GOSP). SONGS, as the site licensee, retained the Oversight Role, with exception of those areas that, as the licensee, would be considered 'non-transferrable'. Examples of those programs were Quality Assurance, Regulatory Affairs and the Employee Concerns Program. While the Company retained responsibility for those programs the DGC developed their own 'parallel' programs that the Company provided Oversight for. In 2017, SONGS completed program transition within one-year following the notice-to-proceed. The overall strategy was driven by three high-level principles: - Allow the DGC the most unfettered execution of the Scope of Work with limited interference and maximum self-governance. With the overriding principle that transitioned programs have a direct link to a basis in regulation or law. - Identify safety and compliance risks, and then bridge the transition of programs from the SONGS to the DGC such that identified risks are minimized and/or mitigated. - Allow the SONGS organization to transition from a Performance role to a primarily Oversight role as the DA. Working collaboratively with the DGC, programs were strategically grouped and sequenced for turnover. Central to the success of transition was fostering a collaborative environment with the DGC, facilitating knowledge transfer, applying schedule rigor, and keeping the team horizontally and vertically aligned to management expectations. SONGS achieved this alignment by embedding the formal process with management expectations for review and acceptance of proposed programs. SONGS' transitioned core programs to a general contractor and transition from a 'perform' organization to an 'oversight' organization. Lessons learned from this experience may benefit other nuclear generating station owners currently evaluating options for site D and D. (author)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Effects of heating rate, quartz particle size, viscosity, and form of glass additives on high‐level waste melter feed volume expansion

Abstract Nuclear waste can be vitrified by mixing it with glass‐forming and ‐modifying additives. The resulting feed is charged into an electric glass melter. To comprehend melting behavior of a high‐alumina melter feed, we monitored the volume expansion of pellets in response to heating at different heating rates. The feeds were prepared with different particle sizes of quartz (the major additive component) and with varied silica‐to‐fluxes ratio to investigate the glass melt viscosity effects. Also, we used additional melter feeds with additives premelted into glass frit. The volume of pellets was nearly constant at temperatures <600°C. After a short period of volume shrinkage at ~600°C‐700°C, foam generation produced massive volume expansion. The low heat conductivity of foam hinders the transfer of heat from molten glass to the reacting feed. The extent of foaming increased with faster heating and higher melt viscosity, and decreased with increasing size of quartz particles and fritting of the additives. Volume expansion data are needed for the mathematical modeling of the cold cap.

Lee, SeungMin↗
NASA NTRS2015

Design of the Brine Evaporation Bag for Increased Water Recovery in Microgravity

The existing water recovery system on the International Space Station (ISS) is limited to 75% reclamation; consequently, long duration space missions are currently unfeasible due to the large quantity of water necessary to sustain the crew. The Brine Evaporation Bag (BEB) is a proposed system to supplement the existing water recovery system aboard the ISS that can to increase water recovery to 99%. The largest barrier to high water recovery is mineral scaling inside the water recovery equipment, which leads to equipment failure; therefore, some water must remain to keep the minerals dissolved. This waste stream is liquid brine containing salts, acids, organics, and water. The BEB is designed to recover this remaining water while protecting the equipment from scale. The BEB consists of a sealed bag containing a hydrophobic membrane that allows water vapor and gas to pass through. It is operated under vacuum, heated, and continuously filled with brine to boil away the water. The water vapor is recovered and the solids are contained inside the bag for disposal. The BEB can dry the brine to a solid block. Ongoing work includes improving the design of the BEB and the evaporator to prevent leaks, maximize the rate of water removal, and minimize energy use and weight. Additional testing will determine whether designs are heat- or mass-transfer limited and the optimal water recovery rate.

Brine Evaporation Bag↗
DOE OSTI2019

The Evolution of DOE/Stakeholder Relationships at the Fernald Preserve, Ohio, Site - 19559

The Fernald Preserve, Ohio, Site is managed by the US Department of Energy (DOE) Office of Legacy Management. It is approximately 29 km (18 miles) northwest of Cincinnati, Ohio, on the site of a former uranium-processing plant established by the US Atomic Energy Commission in 1951. The production mission officially ended in 1991 when it was replaced by a remediation mission. Extensive environmental remediation was subsequently conducted under the Superfund program by the DOE Office of Environmental Management. After most of the remediation was concluded in 2006, the site was transferred to the DOE Office of Legacy Management, which continued comprehensive ecological restoration and is responsible for an ongoing aquifer remediation operation. The site was renamed the Fernald Preserve and opened to the public in 2008 as an undeveloped park, encompassing a diversity of natural habitats native to the area. The site now serves as a community asset, offering a Visitors Center with exhibits that tell the site story, hiking trails, wildlife observation opportunities, meeting spaces for community groups, educational program opportunities, and Interpretive Services personnel to engage the public. There was a long history of community mistrust about government operations at the site, beginning in the 1950's when land for the site was acquired by eminent domain, and continuing when contamination and hazardous waste management concerns were revealed in the 1980's. Resulting media coverage on possible contamination and cover-up concerns was extensive. In 1986, sitewide studies to determine the nature and extent of contamination and to consider cleanup options were instigated. In 1989, the site was placed on the National Priorities List of the Superfund program. Because of the longstanding mistrust held by many stakeholders, DOE faced a very serious challenge in achieving consensus among stakeholder groups about the cleanup levels, waste disposition, and the future uses of the site. Starting in the late 1980's, DOE, the regulators, site contractors and the community took a number of steps over many years to increase trust and achieve consensus among the many stakeholder groups. These steps included establishing a single cleanup mission, involving the community early and often as a critically important stakeholder, creating a citizens taskforce and community envoys, and providing extensive educational outreach. As a result, DOE, regulators, contractors, and community members moved from a position of very little trust to one of increased trust and collaboration among all concerned parties. The lessons learned from the Fernald site can be invaluable in the resolution of difficult environmental issues and should be considered as DOE seeks increased collaboration and consensus with stakeholders to solve other environmental remediation challenges. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2023

Manufacturing Water‐Based Low‐Tortuosity Electrodes for Fast‐Charge through Pattern Integrated Stamping

Achieving high energy density and fast charging of lithium‐ion batteries can accelerate the promotion of electric vehicles. However, the increased mass loading causes poor charge transfer, impedes the electrochemical reaction kinetics, and limits the battery charging rate. Herein, this work demonstrated a novel pattern integrated stamping process for creating channels in the electrode, which benefits ion transport and increases the rate performance of the electrode. Meanwhile, the pressure applied during the stamping process improved the contact between electrode and current collector and also enhanced the mechanical stability of the electrode. Compared to the conventional bar‐coated electrode with the same thickness of 155 μm (delivered a discharge capacity of 16 mAh g −1 at the rate of 3 C), the stamped low‐tortuosity LiFePO 4 electrode delivered 101 mAh g −1 capacity. Additionally, water was employed as a solvent in this study. Owing to its eco‐friendliness, high scalability, and minimal waste generation, this novel stamping technique inspire a new method for the industrial‐level efficient roll to roll fabrication of fast‐charge electrodes.

25 ENERGY STORAGE↗
DOE OSTI2023

Predeployment progress of the Canister Deposition Field Demonstration

This report updates the high-level test plan for evaluating surface deposition on three commercial 32PTH2 spent nuclear fuel (SNF) canisters inside NUTECH Horizontal Modular Storage (NUHOMS) Advanced Horizontal Storage Modules (AHSMs) from Orano (formerly Transnuclear Inc.) and provides a summary of the surface sampling activities that have been conducted to date. The details contained in this report represent the best designs and approaches explored for testing as of this publication. Given the rapidly developing nature of this test program, some of these plans may change to accommodate new objectives or requirements. One goal of this testing is to collect defensible and detailed dust deposition measurements from the surface of dry storage canisters in a marine coastal environment to guide chloride-induced stress corrosion cracking (CISCC) research. Another goal is to provide data for the validation of computational fluid dynamics (CFD) based deposition modeling. To facilitate surface sampling, the otherwise highly prototypic dry storage systems will not contain SNF but rather will be electrically heated to mimic the decay heat and thermal hydraulic environment. Test and heater design is supported by detailed CFD modeling. Instrumentation throughout the canister, storage module, and environment will provide extensive information about the thermal-hydraulic behavior of horizontal dry cask storage systems. Manual sampling over a comprehensive portion of the canister surface at regular time intervals will offer detailed quantification and composition of the deposited particulates from a realistic storage environment. Discussions of a potential host site for the Canister Deposition Field Demonstration (CDFD) are ongoing. Until a host site is chosen, testing of key CDFD hardware components including the heater assemblies, power skid, and remote data acquisition system will continue. Functional testing of the finalized heater assemblies and test apparatus started this fiscal year. These initial heater tests have shown the assemblies are performing within design specifications. Staged surface sampling of a mockup of a canister outside the AHSM on a transfer skid was also performed. Refinements to the sampling procedures and techniques were captured from observation of these activities and lessons-learned debriefs. These updated sampling procedures and techniques are planned to be tested again in the field using the mockup in order to assure personnel are using the most accurate and repeatable methods possible prior to deployment for actual CDFD testing.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Evolution of Stakeholder Relations at the Mound Laboratory-End of DoE's Mission to the Present - 19551

In November 1989, the same month the Berlin Wall fell, the US Environmental Protection Agency (EPA) placed the Mound Laboratory (Mound Plant or Mound site) in Ohio on the National Priorities List (NPL) due to volatile organic compound contamination in the groundwater. As a result of the Cold War ending, the United States sought to greatly reduce the nation's nuclear weapons arsenal, consolidate the US Department of Energy's (DOE) mission, and close many DOE facilities. In 1991, the City of Miamisburg learned that DOE was planning to close the Mound Laboratory. The city spent two years lobbying in Washington, DC, to keep the facility open; however, that effort was not successful. By 1993, DOE, EPA, and Ohio EPA had signed a Federal Facility Agreement that formalized EPA and Ohio EPA oversight of the DOE environmental cleanup of the Mound NPL site under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The decontamination and cleanup of the Mound site fell under two federal laws, CERCLA and the Resource Conservation and Recovery Act. DOE, EPA, Ohio EPA, the City of Miamisburg, and other local stakeholders all agreed that the Mound site should be cleaned up to an industrial/commercial land use standard. This would allow the site to transition into a privately owned business park. In 1994, the City of Miamisburg created the nonprofit Miamisburg Mound Community Improvement Corporation (MMCIC) that would own, market, and redevelop the site. The City also chartered the Mound Reuse Committee to act as an independent advisory organization, composed of representatives from the local community and business, government, education, and special interest groups. In 1994, DOE and the MMCIC entered into a lease agreement that facilitated immediate reuse of site buildings that were no longer required by DOE and did not require remediation. In 1995, DOE, EPA, and Ohio EPA developed the Mound 2000 Process to more effectively use CERCLA Removal Action authority to evaluate and remediate, as necessary, disparate areas of the Mound site. The Mound 2000 process divided the site into smaller, more manageable areas that accelerated cleanup and allowed areas to be reused more quickly. All areas of the Mound site were cleaned up to meet the EPA standard for industrial/commercial land use. The CERCLA process included opportunities for the public to review proposed cleanup strategies. Public input on cleanup and reuse included that from local citizens, businesses, Miamisburg City Council, local schools and financial institutions, Ohio EPA, Montgomery County, and the State of Ohio. In 1998, while site cleanup was still in process, DOE agreed to sell the entire Mound property to the MMCIC for $10.00. The site sales agreement accelerated reuse by allowing DOE to offer ownership of discrete land parcels to MMCIC as soon as EPA confirmed those areas met CERCLA standards for property transfer. This allowed the Mound site to become one of the first former DOE weapons sites to transition to reuse as a privately owned and operated community asset. Many other former DOE production facilities require continued federal ownership to protect the integrity of the environmental cleanup. In 2011, the MMCIC changed its name to the Mound Development Corporation (MDC) and continued to transition the site for reuse as part of the Mound Business Park. The MMCIC/MDC is a nonprofit economic development arm of the City of Miamisburg. DOE supported the economic development efforts with grants and matching funds. Individual land parcels were transferred from DOE to the MDC according to the DOE Mound Land Transfer Process. Ownership of parcels was transferred to the MDC via quitclaim deeds with no repair, replacements, or rebuild of areas. Each parcel's quitclaim deed contains the CERCLA institutional controls. To reduce the property tax burden, the Miamisburg City Council passed an ordinance that allowed the City to accept temporary ownership of specific parcels and hold ownership until the MDC could either lease or sell them. With the exception of one 23-acre parcel that includes the Operable Unit 1 area (site of former sanitary landfill), the entire site has been transferred to the MDC. Today, the former Mound Laboratory site is home to the vibrant Mound Business Park operated by the MDC. The site contains numerous buildings with active businesses and multiple areas suitable for new construction. Private companies continue cutting-edge work that carries forward the legacy of more than 50 years of DOE research, development, production, and inspiration from the former Mound Laboratory scientists, engineers, technicians, and support personnel. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
NASA NTRS1995

Convergent spray process for environmentally friendly coatings

Conventional spray application processes have poor transfer efficiencies, resulting in an exorbitant loss in materials, solvents, and time. Also, with ever tightening Environmental Protection Agency (EPA) regulations and Occupational Safety and Health Administration requirements, the low transfer efficiencies have a significant impact on the quantities of materials and solvents that are released into the environment. High solids spray processes are also limited by material viscosities, thus requiring many passes over the surface to achieve a thickness in the 0.125 -inch range. This results in high application costs and a negative impact on the environment. Until recently, requirements for a 100 percent solid sprayable, environmentally friendly, lightweight thermal protection system that can be applied in a thick (greater than 0.125 inch) single-pass operation exceeded the capability of existing systems. Such coatings must be applied by hand lay-up techniques, especially for thermal and/or fire protection systems. The current formulation of these coatings has presented many problems such as worker safety, environmental hazards, waste, high cost, and application constraints. A system which can apply coatings without using hazardous materials would alleviate many of these problems. Potential applications include the aerospace thermal protective specialty coatings, chemical and petroleum industries that require fire-protection coatings that resist impact, chemicals, and weather. These markets can be penetrated by offering customized coatings applied by automated processes that are environmentally friendly.

Scarpa, Jack↗
DOE OSTI2025

Population Balance Models for Catalytic Depolymerization: From Elementary Steps to Multiphase Reactors

Here, the ongoing accumulation of plastic waste in landfills and in the environment is driving research on chemical processes and catalysts to recycle polymers. Traditional modeling strategies are not applicable to these processes because they involve too many reactants and intermediates, one for each molecular weight and each functionalization. To model the kinetics, we have developed population balance models (PBMs) that account for macromolecular reactants in the bulk and macromolecular catalytic intermediates. These PBMs couple to each other through polymer adsorption and desorption models and to traditional rate equations for small molecule products and co-reactants (like hydrogen or ethylene). The models, in combination with experimental data, are being used in many ways: (i) to test mechanistic hypotheses, (ii) to extract rate parameters, (iii) to quantitatively compare catalyst activities, (iv) to account for mass transfer and vapor–liquid partitioning in two-phase reactors, and (v) to design novel support architectures and catalysts that mimic the processive action of natural depolymerization enzymes. Some key theoretical advances allow PBMs to be constructed from elementary rates and mechanisms, as opposed to traditional formulations with pseudoelementary rate parameters invoked as fitting parameters. We discuss ways to build these models “bottom-up” from first-principles calculations and ways to extract model parameters from “top down” analyses of rate data. The combination provides a quantitative bridge between first-principles calculations and the kinetics of complex macromolecular transformations for polymer upcycling and beyond.

Manis, Lela K. [University of Illinois at Urbana-C↗
DOE OSTI2025

Holistic Microstructure Control Strategies in Photopolymerization‐Induced Phase Separation of Acrylate Systems

Open porous materials, known for their large surface area and interconnected structures, are essential in various applications, including batteries, ion exchange, catalysis, filtration, and electronic waste recycling. A critical aspect of the functionality of porous membranes is the precise control of pore size and morphology. Photopolymerization-induced phase separation (photo-PIPS) offers a convenient and versatile methods for creating porous structures. However, controlling the porous morphology remains challenging due to the complex interplay between thermodynamics, polymerization kinetics, and monomer structures, which makes it difficult to establish the relationship between processing conditions and resulting morphology in photo-PIPS. Herein, a physics-based phase-field model capable of generating and characterizing the microstructures of porous materials based on both average and localized features is developed. Using the phase-field simulations as test bed, the effects of polarity, light intensity, and curing temperature, as well as the previously unexplored roles of chain transfer agents and substrates, on the morphology of the resulting porous microstructure are investigated. Experiments are performed to verify the results predicted by the simulations. This work lays out a comprehensive guide for designing PIPS-derived porous microstructures and offers practical engineering strategies for tailoring microstructure-level topology and size of pores for application-specific needs.

36 MATERIALS SCIENCE↗
NASA NTRS1987

Preliminary design and cost of a 1-megawatt solar-pumped iodide laser space-to-space transmission station

A preliminary conceptual design of a space-based solar pumped iodide laser emitting 1 megawatt of laser power for space-to-space power transmission is described. A near parabolic solar collector focuses sunlight onto the t-C4F9I (perfluoro-t butyl iodide) lasant within a transverse flow optical cavity. Using waste heat, a thermal system was designed to supply compressor and auxiliary power. System components were designed with weight and cost estimates assigned. Although cost is very approximate, the cost comparison of individual system components leads to valuable insights for future research. In particular, it was found that laser efficiency was not a dominant cost or weight factor, the dominant factor being the laser cavity and laser transmission optics. The manufacturing cost was approx. two thirds of the total cost with transportation to orbit the remainder. The flowing nonrenewable lasant comprised 20% of the total life cycle cost of the system and thus was not a major cost factor. The station mass was 92,000 kg without lasant, requiring approx. four shuttle flights to low Earth orbit where an orbital transfer vehicle will transport it to the final altitude of 6378 km.

Deyoung, R. J.↗
DOE OSTI2014

Graphene oxide wrapped Ag{sub 3}PO{sub 4} sub-microparticles with highly enhanced photocatalytic activity and stability under visible light irradiation

Highlights: • Graphene oxide wrapped Ag{sub 3}PO{sub 4} sub-microparticles were prepared. • The photocatalytic activity of Ag{sub 3}PO{sub 4} is increased by 6 times by GO wrapping. • The hybrid photocatalysts exhibited excellent stability. - Abstract: Graphene oxide (GO) wrapped Ag{sub 3}PO{sub 4} sub-microparticles were prepared by in situ deposition–precipitation method. By hybridization of Ag{sub 3}PO{sub 4} with GO nanosheets, a 6-fold enhancement in the photodegradation rate toward orange methyl (MO) under visible light irradiation (λ ≥ 420 nm) was observed compared with the pure Ag{sub 3}PO{sub 4} sub-microsparticles. The hybrid photocatalysts also exhibited excellent stability in the successive MO degradation experiments. The highly enhanced photocatalytic activity and stability were mainly attributed to the quick transfer of the photogenerated electrons from Ag{sub 3}PO{sub 4} to GO nanosheets, which could effectively suppress the electron–hole pairs recombination and thus inhibit the photocorrosion of Ag{sub 3}PO{sub 4}. These high-efficient and stable hybrid photocatalysts were expected to show considerable potential applications in wastewater treatment and water splitting.

36 MATERIALS SCIENCE↗
DOE OSTI2012

Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (∼49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2024

Mixed waste contamination selects for a mobile genetic element population enriched in multiple heavy metal resistance genes

Abstract Mobile genetic elements (MGEs) like plasmids, viruses, and transposable elements can provide fitness benefits to their hosts for survival in the presence of environmental stressors. Heavy metal resistance genes (HMRGs) are frequently observed on MGEs, suggesting that MGEs may be an important driver of adaptive evolution in environments contaminated with heavy metals. Here, we report the meta-mobilome of the heavy metal-contaminated regions of the Oak Ridge Reservation subsurface. This meta-mobilome was compared with one derived from samples collected from unimpacted regions of the Oak Ridge Reservation subsurface. We assembled 1615 unique circularized DNA elements that we propose to be MGEs. The circular elements from the highly contaminated subsurface were enriched in HMRG clusters relative to those from the nearby unimpacted regions. Additionally, we found that these HMRGs were associated with Gamma and Betaproteobacteria hosts in the contaminated subsurface and potentially facilitate the persistence and dominance of these taxa in this region. Finally, the HMRGs were associated with conjugative elements, suggesting their potential for future lateral transfer. We demonstrate how our understanding of MGE ecology, evolution, and function can be enhanced through the genomic context provided by completed MGE assemblies.

59 BASIC BIOLOGICAL SCIENCES↗
DOE OSTI2017

Vattenfall Decommissioning Planning in Sweden - 17544

A rapid decrease in the power prices in the Nordic market for the last three years has drastically reduced the profitability of the nuclear power plants in Sweden. This has resulted in a very quick re-evaluation of the optimal life-term of the older generation, from the 1970's, nuclear units in Sweden. Hence, it was decided last year to shut-down the Vattenfall Ringhals-1 BWR and the Ringhals-2 PWR by 2020 and 2019, respectively, for financial reasons. Before that decision, the planning had been to operate the units until 50 years life-time, i.e. 2024 and 2025. This decision resulted in a prompt start of the planning for decommissioning of the two units. The planning started with a project, called AVANS, to ensure that the overall planning and to-be-developed organisations had well defined requirements and a common platform. Another project, STURE, was started to ensure the continued operation and in some case movement of common site functions to the two younger units on the Ringhals site, i.e. the PWRs Ringhals-3 and Ringhals-4. This project also has the responsibility to optimise operation of Ringhals-1 and Ringhals-2 to EOL and the subsequent removal of the nuclear fuel from the units after necessary cool-down. A third project started is the actual decommissioning project, TYKO, benefiting from experience gained and staff involved in still ongoing decommissioning of a legacy materials reactor, i.e. the Studsvik R2/R2-0 reactor. The planning and experience to date for the three projects will be presented in the paper, as well as lessons-learned and future plans, including some critical items identified wrt dismantling and site function transfer. Half of the nuclear units in Sweden, six units, and one legacy power reactor, will be starting decommissioning within the next few years. Impacts on the back-end system; the financial situation, with respect to the state-controlled financial funding; and the supplier market are discussed in the paper. Furthermore, the planning process and the planned management of the interfaces between the involved organisations is described. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification

Expanding spent fuel dry storage activities worldwide are increasing demands on safeguards authorities that perform inspections. The European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) require measurements to verify declarations when spent fuel is transferred to difficult-to-access locations, such as dry storage casks and the repositories planned in Finland and Sweden. EURATOM makes routine use of the Fork detector to obtain gross gamma and total neutron measurements during spent fuel inspections. Data analysis is performed by modules in the integrated Review and Analysis Program (iRAP) software, developed jointly by EURATOM and the IAEA. Under the framework of the US Department of Energy–EURATOM cooperation agreement, a module for automated Fork detector data analysis has been developed by Oak Ridge National Laboratory (ORNL) using the ORIGEN code from the SCALE code system and implemented in iRAP. EURATOM and ORNL recently performed measurements on 30 spent fuel assemblies at the Swedish Central Interim Storage Facility for Spent Nuclear Fuel (Clab), operated by the Swedish Nuclear Fuel and Waste Management Company (SKB). The measured assemblies represent a broad range of fuel characteristics. Neutron count rates for 15 measured pressurized water reactor assemblies are predicted with an average relative standard deviation of 4.6%, and gamma signals are predicted on average within 2.6% of the measurement. The 15 measured boiling water reactor assemblies exhibit slightly larger deviations of 5.2% for the gamma signals and 5.7% for the neutron count rates, compared to measurements. These findings suggest that with improved analysis of the measurement data, existing instruments can provide increased verification of operator declarations of the spent fuel and thereby also provide greater ability to confirm integrity of an assembly. These results support the application of the Fork detector as a fully quantitative spent fuel verification technique.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2025

Application of Raman Spectroscopy to Determine Uranium Content in ADUN Solution

The work presented in this report is part of the ongoing efforts to address the nuclear material control and accounting needs for advanced reactor fuel fabrication facilities. This work was supported by the Materials Protection, Accounting, and Control Technologies (MPACT) program under the US Department of Energy Office of Nuclear Energy‘s Nuclear Fuel Cycle and Supply Chain program. The activities and engagements under the MPACT program are designed to support a robust US civilian nuclear energy enterprise. In the work described in this report, we supported MPACT objectives by developing measurement techniques that could be used for material accounting and process monitoring and by working with industry partners to identify existing gaps and areas for improvement. Oak Ridge National Laboratory has been working with commercial tristructural isotropic (TRISO) fuel fabricators such as Standard Nuclear to develop technology for rapid and cost-effective uranium content assessment. This work has focused on demonstrating advanced measurement techniques (e.g., Raman spectroscopy) that can be used for rapid, reliable, and cost-effective routine measurements of uranium content in feed solutions and liquid waste streams as well as for monitoring in-line process measurements and product streams. Specifically, this report explores techniques for accurately determining uranium content in acid-deficient uranyl nitrate (ADUN) solutions and detecting low uranium concentrations in ammonia solutions. Developing such measurement techniques will benefit TRISO fuel fabrication facilities, facilities involved in other parts of the fuel cycle that require online monitoring of aqueous solutions, and potentially molten salt fuel reactors. This work supports developing Raman spectroscopy procedures to determine uranium concentrations in ADUN solutions, which are used as feedstock in the sol–gel process for creating TRISO fuel. Some additional benefits of using Raman spectroscopy for uranium quantification in fabrication facilities include enabling online monitoring of the chemical process, which would provide near real-time feedback; eliminating the need for sample transfers, preparation, or dilution; providing nondestructive measurements; and user friendliness. In this fiscal year, FY25, we determined the identity of the unknown Raman band at approximately 853 cm−1 that was discovered in ADUN Raman spectra in FY24, created calibration curves and determined uranium concentrations of two ADUN solutions, and compared the Raman results to results obtained from inductively coupled plasma mass spectrometry and Davies–Gray titration. Furthermore, we have identified focus areas for experimentation in future fiscal years. A key result is that the accuracy of using Raman can provide accuracy comparable to destructive analysist techniques, With a well-developed calibration curve, using standards and a large number of samples (more than five samples), uncertainty on the order of 1%–3% is achievable. Given that the uncertainties achieved by Raman spectroscopy were on the order of the uncertainties achieved using ICP-MS, we conclude that with a well-developed procedure Raman spectroscopy can be used to determine uranium concentrations in ADUN solutions for NMC&A applications. The benefits of such an approach are that the time and effort will be less than that of comparable destructive analysis techniques, with approximately the same level of technical expertise. This will be attractive to operators of fuel fabrication facilities as it will lower costs and improve efficiencies.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2025

Can the Hock Process Be Used to Produce Phenol from Polystyrene?

Polystyrene (PS) is a widely used thermoplastic polymer, but its very low recycling rate has motivated consideration of chemical conversion strategies to convert waste PS into value-added products. Oxidation methods have been widely studied, but they typically generate benzoic acid, a product with a relatively low market demand. Phenol is a higher volume chemical that would be an appealing target, but no methods currently exist for the conversion of PS into phenol. The repeat unit in PS closely resembles cumene, the primary feedstock used to produce phenol through the Hock process. Here, we investigate prospects for adapting the Hock process to PS, generating hydroperoxides through the autoxidation of benzylic C–H bonds followed by the acid-promoted rearrangement of the hydroperoxides to afford phenol and a partially oxygenated polymer. Experimental and computational studies of dimeric and trimeric PS model compounds show that neighboring phenyl rings impose conformational constraints that raise the barrier to hydrogen-atom transfer from the tertiary benzylic C–H bond. These effects are also evident with PS and contribute to lower yields of phenol when PS is subjected to Hock process conditions. Furthermore, these results provide valuable insights that have important implications for other efforts that seek to adapt small-molecule reactivity to polymeric feedstocks.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗