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DOE OSTI2018

Update on Development of a U.S. Rail Transport Capability for Spent Nuclear Fuel and High-Level Waste - 18518

The U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) is laying the groundwork for implementing an integrated nuclear waste management system. This includes preparing for future large-scale transport of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) since transport will be a necessary component of an integrated waste management system. This paper provides an overview of the progress to date, and discussion of the path forward related to designing, fabricating and testing prototype railcars for rail transport of SNF from commercial nuclear power reactor sites when a receiving site becomes operational. (authors)

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DOE OSTI2016

Overview of LWR Accident Tolerant Fuel Development in the United States

The U.S. Department of Energy (DOE) has conducted research and development (R and D) for enhanced, accident tolerant fuels (ATF) for light water reactors (LWRs) since 2012. The recently released Road-map to Congress for 'Development of Light Water Reactor Fuels with Enhanced Accident Tolerance' establishes the attributes that are desired for fuels that will exhibit enhanced accident tolerance and defines a path forward for the necessary R and D activities that will result in a lead fuel rod (LFR) or assembly (LFA) insertion in an operating, commercial LWR by 2022 to demonstrate the possibility of these advanced technologies. The aggressive development timeline is directed by Congressional language in the Senate Appropriations Committee Report (Senate Report 112-75), included in the Fiscal Year (FY) 2012 Energy and Water Development Appropriations Bill. ATF development is intended to be impactful to the current fleet of LWRs and future Generation III+ reactors. The development, future licensing and utility adoption of ATF technology will empower development of advanced technologies with safety significance. The work has progressed significantly since 2012, with multiple fuel and cladding concepts currently undergoing fundamental R and D including in-pile irradiation and out-of-pile testing to measure fundamental properties and to demonstrate performance under expected conditions. (authors)

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DOE OSTI2016

Microstructural Characterization of In-reactor Corrosion Tested Hastelloy N{sup R} and 316 Stainless Steel

The success of the Molten Salt Reactor Experiment (MSRE) at the Oak Ridge National Laboratory (ORNL) in the period 1950's-70's has rekindled the interested in molten salt-cooled reactors. The most recent form of this type of reactor, the Fluoride salt-cooled High-temperature nuclear Reactors (FHRs) is emerging as a leading reactor concept for the next generation nuclear reactors because it offers, among other benefits, a high degree of passive safety, high thermal efficiency, and low spent fuel. Since 2011, two three-year Integrated Research Projects (IRPs) were awarded by the U. S. Department of Energy (DoE) to the Massachusetts Institute of Technology (MIT) in partnership with the University of California, Berkeley and the University of Wisconsin-Madison to develop a 'path forward' for the development of the FHR. One primary challenge in these projects is to evaluate the corrosion and compatibility of structural alloys in the potential primary coolant of molten Li{sub 2}BeF{sub 4} (FLiBe) salt at 700 deg. C in a neutron irradiation environment. In support of structural materials development for the FHR, the static in-reactor corrosion tests of two promising alloys, nickel-based Hastelloy N{sup R} and 316 stainless steel, in {sup 7}Li-enriched molten FLiBe have been conducted in both metal-lined and graphite crucibles in the MIT nuclear research reactor in 2013. This work focuses on the microstructural characterization of the in-reactor corrosion tested alloys for understanding of their performance in high-temperature molten FLiBe salt. Our preliminary results indicate significant thermal effects, graphite effects, and irradiation effects on the alloys' performance in high-temperature molten FLiBe salt, particularly for the in-reactor corrosion tests. The neutron irradiation induces tritium generation in molten salt which could combine with fluorine ions to form corrosive HF to dramatically attack alloys. Additionally, the neutron irradiation introduces structural defects into alloys which probably alter alloys' corrosion resistivity to high temperature molten FLiBe salt. The effect of graphite on the alloys' corrosion in a nuclear reactor is also possibly different from the out-of-reactor corrosion. All these issues will be better understood by characterizing the microstructure of in-reactor corrosion tested alloy samples in our near future plans. The experimental data in this study provides valuable input for evaluating structural materials performance in the FHR. (authors)

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DOE OSTI2019

Why Cleanup Acceptance Is Running into Conflicts - Off-site Disposal Versus On Site Disposal - 19068

For years the U.S. Department of Energy (DOE) identified several sites to receive shipments of various types of wastes. However, with the backlog at the Waste Isolation Pilot Plant (WIPP), the inability to license Yucca Mountain, and the agency's desire to expedite cleanup, DOE is trying to 'dispose of' or 'store' more waste belonging to the Federal government on-site. Some states and communities that were 'promised' disposal of DoE's waste in geologic repositories and licensed landfills in arid locations, are now being told that on-site disposal is the best path forward. Competition for resources is forcing more sites to focus on near term cost savings of on-site disposal, rather than develop comprehensive life-cycle estimates representing a more realistic picture of costs associated with isolating radioactive and other hazardous materials on-site in perpetuity. The paper explores the issues and possible solutions in a case study on proposed on-site disposal of DOE waste, and concludes that DOE needs community support and community acceptance to successfully implement the agency's cleanup mission. Ongoing dialogue with the community saves both time and money but more importantly, cooperation helps ensure that effective long-term cleanup occurs. (author)

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DOE OSTI2019

Update on Development of a U.S. Rail Transport Capability for Spent Nuclear Fuel and High-Level Waste - 19092

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DOE OSTI2019

Low-Level Waste Minimization and Management Planning at the Western Waste Management Facility, Ontario Power Generation - 19235

The purpose of this study was to examine the strategies intended to mitigate the temporary storage restrictions for Low-Level radioactive waste at the Western Waste Management Facility to enable continued accommodation of waste generation rates, and to recover storage capacity from 2018-2023 to optimize long-term sustainability for radioactive waste management. The management options considered were based on existing waste processing technologies and programs available at the Western Waste Management Facility, in combination with third party volume-reduction services. Completed analysis measured the consumption of Low-Level Waste storage space as influenced by the projected volumes from nuclear generating stations, and the various processing scenarios developed; such as reducing the volume of surplus processable waste on-site, and the reduction of specific waste streams previously considered to be non-processable. Results from the quantitative analysis indicated which strategies will be most effective for minimizing waste volumes for long-term storage and for recovering low-level storage space at the Western Waste Management Facility. The strategic path forward is presented in short- to long-term management objectives. Results from this study will contribute to the waste stream planning and management of major reactor refurbishment projects and to the technological advancements and innovation of radioactive waste processing and minimization. With further understanding of the refurbishment-specific waste types and volumes, it is expected that Nuclear Waste Management and the nuclear generating stations will achieve increasingly improved minimization results with the progression of each refurbished reactor. (author)

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DOE OSTI2019

International Government Collaboration in ISD (In Situ Decommissioning/In Situ Disposal) - 19261

In situ decommissioning (ISD) is considered by IAEA as the permanent entombment of a legacy facility in 'a structurally long lived material' (e.g. concrete) and is considered a solution only under 'exceptional circumstances' (e.g. following a severe accident). However, this definition of ISD as 'only' entombment is not universally accepted; the approach has been implemented as a decommissioning approach by the US Dept of Energy in the past decade at the Savannah River Site (P and R reactors)2,3, the Hanford site (U Canyon) and at the Idaho site (CP601, CP640 and CP633). The application of ISD outside of the United States has been much less common for large facilities although its use for underground substructures (e.g. discarded pipelines) is commonplace. Proponents of ISD consider it beneficial since it eliminates the need to remove, package and transport contaminated equipment from a nuclear legacy site to a disposal facility and it maximizes the use of an existing nuclear site footprint by consolidating equipment in one place. ISD is considered to offer major safety benefits to both workers and the public, as well as major cost and schedule benefits to Government. Opponents of the approach cite the fact that, following ISD, the decommissioned facility has effectively become a long-term waste disposal site and that regulations pertaining to long term waste disposal have been circumvented. Given the increasing pressure on environmental cleanup budgets and schedules around the world, countries such as the United Kingdom, Canada and Japan are considering ISD in its various forms as a potential path forward for decommissioning certain facilities in lieu of the more traditional approaches of either deferred decommissioning or immediate decontamination/demolition. To address this emerging area of decommissioning, a Governmental Technical Information Exchange meeting was held in December 2017 at the DOE Savannah River Site in Aiken, SC, to bring together responsible parties from the US Dept of Energy (DOE), Atomic Energy of Canada Ltd (AECL), the UK Nuclear Decommissioning Authority (NDA) and the Japanese Atomic Energy Agency (JAEA) and those countries' respective regulatory agencies to share information about respective 'best practices' and challenges with ISD. Representatives from organizations such as IAEA and US Nuclear Regulatory Commission (US NRC) also participated to discuss their organizations' perspectives and position on ISD. Following the meeting, a series of Working Groups were established which have continued the dialogue in three key areas 5; - ISD-Defined: Identify and share case-specific ISD solutions which allows for the full spectrum of needs and which demonstrate that 'entombment' is not the only definition of 'ISD'. - Regulatory - Share and discuss regulatory concerns and challenges with ISD; - Benchmarking - Share information to support informed and transparent decision-making in ISD. This paper discusses the plans for ISD in some of the countries involved in the December meeting and provides an update on the topics being discussed, and progress being made, by the Working Groups that were formed at the meeting. (authors)

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DOE OSTI2019

Deep Isolation - Innovation for the Storage and Disposal of High-level Waste and Spent Nuclear Fuel - 19367

Deep Isolation, Inc. is a private, Berkeley based company that has brought innovation to nuclear waste disposal. Deep Isolation has developed a disposal technique that adapts mature drilling technology and customizes it for the purpose of providing a safe and secure solution. Though the stalled nuclear waste program in the US has created unwanted burdens and costs, it has also provided object lessons which Deep Isolation has learned from and designed a novel approach. The solution proposed by Deep Isolation combines the best of the geosciences and social sciences to present the US and other countries with an optimized and tailored approach to disposing of a variety of nuclear waste. This system can complement existing potential storage and disposal sites, or in the case of countries with smaller amounts of waste--the national solution. Deep Isolation innovates where others have stalled and offers a means of deep geological disposal that costs less, takes less time to implement, and cuts down and in some cases eliminates the need for transportation of the waste. The technical solution optimized by Deep Isolation uses established directional drilling technology from the oil and gas industry to drill a vertical drill hole thousands of meters deep and then transition to a horizontal drill hole that is thousands of meters in length. The target media is in or below shale formations, which are present at various depths throughout much of the United States and throughout the world. The availability of suitable geology allows for permanent disposal at multiple locations - including existing nuclear sites, without a need to transport the waste to a central repository. This innovative solution not only offers options for commercial used nuclear fuel and defense spent nuclear fuel and high-level waste, but also other nuclear wastes such as those considered by DoE's past deep bore-hole program, i.e. cesium and strontium capsules. Greater-Than-Class-C (GTCC) waste is also an opportunity for Deep Isolation. DoE's preferred alternative for GTCC includes 'land disposal at generic commercial facilities.' Deep Isolation could provide safe, secure, and permanent disposal at a commercial facility. Deep Isolation complements the technical innovation with best practices from the social sciences. In acknowledgement that the past challenges to implement nuclear waste disposal facilities have been primarily due to socio-political failings, we have designed a means to deeply engage with public and stakeholders. Our approach is committed to partnering with communities, local jurisdictions, states, and Tribes to determine a path forward that benefits all involved, that is fully transparent, collaborative and accountable. (authors)

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DOE OSTI2019

Panel Session 73: DOE-EM End-State Contracting

US DOE-EM's new end-state contracting model, the ID/IQ (Indefinite Delivery/Indefinite Quality) approach, is intended to give EM the flexibility to better define discrete scopes of work for site closure or end states. This is the result of several years of dialogue between industry and DOE about the way to collectively improve the way to do business more safely, quickly and cost effectively. This model requires a fine balance between incentives and clearly defined end states, with the ability for contractors and DOE to react quickly to respond to changes. By March 6, DOE and industry were one month into the new end-state contracting model with two requests for proposals issued and contractors responding. The purpose of the panel was to hear from DOE and industry about the status so far. DOE and the contractor community are generally supportive of the new model, but it will require closer partnership and a new mindset and approach among DOE, contractors, regulator and the workforce. This panel focused on the implementation of DOE EM's new End State Contracting Model, which uses a single-award ID/IQ approach to give EM the flexibility to better define discrete scopes of work for site closure or end states. The panelists provided their perspective on the initial implementation of the new approach and the path forward for upcoming opportunities utilizing this model. Presentation proposed: DOE EM End State Contracting (Tamara Miles, US DOE (USA))

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DOE OSTI2019

Panel Session 111: Nuclear Power Plant Onsite SNF storage, ISFSIs and Failed Fuel Handling Issues

This panel session provided updates on several issues seen in developing, operating independent spent fuel storage installations (ISFSIs), Damaged Fuel and aging management recent activities. Presentations proposed include: 1 - Spent Nuclear Fuel Management Activities at Holtec (Myron Kaczmarsky, Holtec International (USA)); 2 - INL Spent Fuel Management: Challenges and Path Forward for Dry Storage (Josh Jarrell, Idaho National Laboratory (USA))

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DOE OSTI2019

Overview of Novel Canadian Approaches for Decontamination of Solid Radioactive and Mixed Waste - 19476

The availability of decontamination-for-release technology options provide a path forward to economically decontaminate radioactive metallic waste and enable its disposal as clean scrap metal, to decontaminate tools/equipment for unrestricted refurbishment or reuse, and to carry out inspection of in-service components. Projects involving management of solid mixed waste pose complex technical challenges that require the development and application of novel decontamination processes. The objective of this paper is to present project case studies that provide an overview of Kinectrics' experience with the decontamination of solid radioactive and mixed waste. Novel approaches to decontamination, recent developments, key results and lessons learned will also be discussed. (authors)

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DOE OSTI2019

Savannah River Site H-Canyon Collaborative Advanced Technology Demonstration (ATD) Program Review - 19499

The purpose of the Department of Energy-Environmental Management Office of Technology Development's (DOE-EM TD) Science of Safety (SOS) Robotics Initiative is to pull innovative commercial off the shelf (COTS) and near ready technologies to the field to expedite remaining EM mission clean up and enhance worker safety. A goal of this program is to demonstrate to DOE facilities the value of these available new technologies and their potential uses to solve difficult problems. In support of this goal, the Savannah River Site (SRS) H-Canyon Air Exhaust (HCAEX) tunnel biannual inspection task has been selected to demonstrate and evaluate the benefit of pulling advanced technology solutions to EM facilities. This is a highly collaborative task facilitated by SRNL and engaging SRS H-Canyon facility stakeholders, National Laboratory robotic and concrete inspection SMEs and university robotic and sensor researchers. Presently, the SRS HCAEX tunnel inspection consists of a visual examination to evaluate the structural integrity of the tunnel. Personal access is prohibited in the tunnel due to extreme conditions, thus the examination is accomplished remotely by deploying cameras mounted on a robotic crawler deployed into the tunnel. While the ability to see inside the tunnel in recent years has been highly valuable, it is desirable to have a better understanding of the environment to support a more thorough structural analysis and for long term planning purposes. This higher order of understanding can be accomplished through advanced COTS sensors and tools and those currently in development and near ready. The advanced technologies selected for demonstration will be evaluated for hosting on the FY19 HCAEX tunnel inspection crawler platform. The HCAEX ATD task is expected to be performed over a two-year period with year one now concluding. At WM2018, we presented the H-Canyon stakeholder's high priority inspection and remote handling needs, the collaboration team and the planned process of developing an integrated solution. This presentation will review the initial scope and inspection needs, then discuss the past year's progress to address these needs. The discussion includes the results of the Concrete Integrated Product Team (CIPT) formed to evaluate promising concrete NDE inspection technologies and a Lidar based tunnel mapping sensor suite solution. Highlighted in the discussion will be the engagement and pulling of university developed research and development to include student engagement through the formation and hosting of the SRNL Robotics and Sensors Intern team and collaboration with MSIPP funded Robotic Arm Concrete NDT Inspection University researchers. Lastly, the path forward to complete the demonstration will be presented. (authors)

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DOE OSTI2019

A Flaw Stability Analysis for the Savannah River Site 3H High-Level-Waste Evaporator - 19548

The Savannah River Site (SRS) 3H high-level-waste Evaporator (242-25H) entered service in January 2000 and was discovered to be leaking in February 2016. It was robotically repaired and resumed operation in July 2018. During initial restart in December 2017, salt deposits were discovered on the evaporator's lower shell near welds, indicating two more small leak sites. The leak sites have an estimated hydraulic diameter of about 0.1 mm or less - about the diameter of a human hair. The estimated leak rates are about a factor of 10,000 smaller than the robotically repaired leak. An API 579-1/ASME FFS-1 fitness-for-service evaluation determined that if the leak sites are cracks, then they would need to be about 60 mm long (∼ 2 inches) to actively and catastrophically grow. Furthermore, a crack of this length would have been detected earlier since it would leak thousands of liters per day. The evaporator was designed with engineered features that minimize risks posed by these small leaks. The path-forward involves operating the evaporator in a deliberate manner with enhanced surveillance. The 3H Evaporator is key to SRS safely and timely reducing its 130 million liter liquid high-level-waste inventory, closing remaining waste tanks, and reducing associated risks to workers, the public, and the environment. (author)

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DOE OSTI2019

Characterization Techniques for TRU Waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory - 19610

Since the first reactor went hot in 1942, there has been a never ending desire to improve the nuclear reactor and the fuel that it burns. The Idaho National Laboratory has been a key player in reactor and fuel development. As more research projects begin, the spectrum of waste parameters grows. Over the years, the Analytical laboratory (AL) at the INL Materials and Fuels Complex (MFC) has supported a large range of various research projects. Each project brings its own challenge and analytical technique that, in turn, yields its own unique waste parameters. The AL Hot Cells at INL consist of 6 small cells that can support around 12 different fuel research projects at a time along with infrastructure and environmental samples. Each different project yields different levels of transuranic (TRU) material, RCRA constituents, dose, and contamination levels. The waste parameters from each project dictate a path forward for the waste as Low-Level Waste (LLW), Contact Handled TRU (CH-TRU), Mixed Contact Handled TRU (M-CH-TRU), Remote Handled TRU (RH-TRU), or Mixed Remote Handled TRU (M-RHTRU). With visual examination techniques and process knowledge as an aid, there have been waste handling methods developed that allow debris and sample material to be segregated. Unique characterization mechanisms have been applied for each debris and sample material that are generally more accurate than smear and surface contamination data. For debris found in the Hot Cells, analytical data is gathered and conservatively summarized for each fuel type and research method. This consists of data from Quadrupole Inductively Coupled Plasma Mass Spectrometry (Q-ICP-MS), Gamma Spectroscopy, and some data verification through Thermal Ionization Mass Spectrometry (TIMS) and Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS). This data gives a range of TRU isotope concentrations. Fuel age is taken into account to determine the dominant TRU activity isotopes. Cesium concentrations are also gathered. Each parameter/fuel type then ties a measured Cesium number to TRU content based on historical analytical data. Debris in the hot cells is segregated by project and packaged in individual 2 gallon metal paint cans. Each can is counted by gamma spectroscopy in a calculated and measured geometry. Using process knowledge to determine the fuel or project type, newly counted cesium numbers can be applied to the historic analytical data and TRU content can be estimated. The TRU content allows waste debris to be segregated between CH-TRU and RH-TRU. Packaging techniques can allow for the minimization of RHTRU waste. Sample material received into the AL must be dissolved into a liquid matrix in order to be analyzed in most cases. When analysis is complete, these liquids go through a consolidation, complexation, neutralization, and solidification process where real time analytical data can be used to calculate TRU content and RCRA constitutes. These calculations allow for no further analytical data to be gathered. The waste matrix is considered stable and acceptable by all Acceptable Knowledge (AK) documents. The unique techniques used in characterizing and handling the Analytical Laboratories Hot Cell waste can be applied to various situations and various laboratories. They allow for more accurate data for waste constituents and also for the minimization of RH-TRU waste. (authors)

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DOE OSTI2019

X-Ray Fluorescence Quantitative and Qualitative Analysis Using Micro Glass Beads

The fused glass bead method is the accepted 'best practice' method of preparation of samples for X-ray fluorescence (XRF) analysis. It minimizes the effects of sample heterogeneity and simplifies calibration by dissolving the sample into a uniform glass matrix. Glass fusion XRF samples are typically prepared by grinding sample powder with Lithium Tetraborate / Lithium Bromide and fusing the mixture at 1000 deg. C. In most cases sample-to-flux ratios of between 1:1 to 1:10 are used (1:1 for determination of trace elements and 1:10 for major elements). Typical sample mass consumed is in the range of 1000 to 2500 mg. It would be advantageous to reduce this sample mass in cases where the sample material is rare, valuable or highly radioactive. This study examines the effects of using lower sample-to-flux ratios and smaller fusion bead size on the detection and quantification of major and trace elements by XRF analysis. We have employed a micro fused glass bead process, using sample-to-flux ratios of 1:10, 1:15 and 1:25, to determine the effects on measurement precision, accuracy and detection limit. Objectives: - Created micro fused glass beads of a series of standards and andesite sample with sample-to-flux ratios of 1:10, 1:15 and 1:25. - Perform an qualitative analysis of the different sample-to-flux ratio micro beads and compare the results with the 1:5.3 beads routinely used at SRNL. - Quantitate the major components in the different sample-to-flux ratio micro beads using a wavelength dispersive x-ray fluorescence instrument. Advantages: - Reduce sample amount needed. - Speed up waste tank characterization. - Reduce personnel exposure. - Potential sealed source. Fused micro glass beads with sample-to-flux ratios of 1:10, 1:15 and 1:25 were created using sample amounts of 123 mg, 82 mg and 52 mg respectively. It was possible to detect most of the major oxides and some trace elements in the fused micro glass beads with different sample-to-flux ratios. The quantitative analysis showed good linear correlation between the intensity of the analysis and the concentration of the elements. Good precision and accuracy results were obtained for the majority of the major oxides in the three fused micro glass beads with different sample-to-flux ratios. Path Forward: Enhance the precision and accuracy of the method by optimizing different sample preparation steps, such as weighing and sample transfer. Continue to increase the sample-to-flux ratio to determine the minimum amount of sample needed to perform a multielement analysis. Consider the use of synthetic standards to lower the detection limit of the analysis. Used the micro bead sample preparation method to analyze radioactive samples.

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DOE OSTI2020

Panel Session 134: Stakeholder Involvement in Consolidated ISF Storage, Disposal, and Transportation Initiatives

Planning of activities related to waste storage, transportation, and disposal requires involvement and engagement on the parts of both regulators and stakeholders. There have been challenges felt by both parties, which has led to discussions about how to best proceed with projects not just from a technical perspective, but how to create better relationships between the general public and scientific community. This panel was designed to highlight lessons learned, best practices, and next steps in anticipated projects. This panel focused on the current efforts undertaken by initiatives to involve stakeholders for the success of ISF Storage and Disposal facilities. For example, two license applications were submitted to the US NRC by two private entities - Interim Storage Partners (WCS, Inc, and Orano) and Holtec, Inc./ELLA - for consolidated ISF in West Texas and in NM (respectively). This panel discussed elements needed for success in engaging various stakeholders at all levels of the project life cycle, and can include lessons learned from previous projects. Panelists with presentations: Stakeholder Engagement in SNF Storage and Disposal (Miriam Juckett); Stakeholders, Siting and Nuclear Waste Disposal -Thoughts on a Path Forward (Jim Hamilton)

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DOE OSTI2020

Panel Session 94: US DOE Procurement Opportunities and End-State Contracting Model Status

This panel focused on DoE's procurement implementation strategy and planned activities for its first-tier contractors (Tier 1 procurements). This panel also focused on the implementation status of DoE's End State Contracting Model, which uses a single-award ID/IQ approach to give DOE flexibility to better define discrete scopes of work for site closure or end states. The panelists provided their prospective on progress toward the implementation of this new approach, lessons learned and the path forward for upcoming opportunities utilizing this contracting model. Panelists with presentations: EFCOG (Billy Morrison); DOE Procurement Opportunities - 4 Ways for Small Business Participation (Anne Marie Bird); US DOE Procurement and Contracting Opportunities (Aaron Deckard)

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DOE OSTI2020

Update on Development of a U.S. Rail Transport Capability for Spent Nuclear Fuel and High-Level Waste - 20466

This paper provides an overview of the progress to date, and discussion of the path forward, related to designing, fabricating and testing prototype railcars that will comply with the safety standard S-2043. This standard was developed by the Association of American Railroads (AAR) specifically for railcars used to transport High-Level Radioactive Material (HLRM). AAR defines the term HLRM to include both spent nuclear fuel (SNF) and high-level radioactive waste (HLW). DOE is in the process of developing and testing prototype railcars that will satisfy Standard S-2043. This is a technical paper that does not take into account contractual limitations or obligations under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (Standard Contract) (10 CFR Part 961). For example, under the provisions of the Standard Contract, spent nuclear fuel in multi-assembly canisters is not an acceptable waste form, absent a mutually agreed to contract amendment. To the extent discussions or recommendations in this paper conflict with the provisions of the Standard Contract, the Standard Contract governs the obligations of the parties, and this paper in no manner supersedes, overrides, or amends the Standard Contract. This paper reflects technical work which could support future decision making by the Department of Energy (DOE or Department). No inferences should be drawn from this paper regarding future actions by DOE, which are limited both by the terms of the Standard Contract and a lack of Congressional appropriations for the Department to fulfill its obligations under the Nuclear Waste Policy Act including licensing and construction of a spent nuclear fuel repository. (authors)

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