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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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At least 613 records · Page 34
All sourcesNASA NTRSDOE OSTI
DOE OSTI2025

Repurposing Offshore Infrastructure for Clean Energy (ROICE) vs. Decommissioning – Commercial Considerations

Abstract The Repurposing Offshore Infrastructure for Clean Energy (ROICE) Program, a collaboration of the energy industry and University of Houston, proposes extending the life of up to 1,500 oil and gas platforms in the Outer Continental Shelf of the Gulf of Mexico, USA. Rather than decommissioning or converting them to underwater reefs at the end of their oil and gas production phase, the platforms could be transformed for 10–20+ years of renewable energy development, such as green hydrogen production or carbon dioxide injection and storage, resulting in significant economic, environmental, and social benefits. ROICE has already published papers on the technical and regulatory considerations for such repurposing projects. This paper focuses on the commercial considerations needed to ensure ROICE projects are economically viable and sustainable for all involved. There are potentially many entities that can come together to progress a repurposing project, including oil and gas asset owners, operators, investors, developers, contractors, manufacturers, and regulators. This paper looks at possible combinations of these entities in a ROICE project team and the various commercial agreements that will be needed to ensure a mutually successful outcome. The paper proposes adapting existing industry agreements and templates to suit, including asset transfer agreements (ATA), asset purchase agreements (APA) and joint purchasing agreements (JOA). An ATA or APA can be drafted to address the obligations and issues involved in the sale or transfer of an existing oil and gas facility to the developer, operator, non-operating interests, and financial investors in a ROICE project, while a JOA can be drafted to govern the rights, obligations, and financial requirements of the parties involved in the development and operation.

Legge, G. [Endeavor Management, USA]↗
DOE OSTI2013

Genome sequence of the free-living aerobic spirochete Turneriella parva type strain (H T ), and emendation of the species Turneriella parva

Turneriella parva Levett et al. 2005 is the only species of the genus Turneriella which was established as a result of the reclassification of Leptospira parva Hovind-Hougen et al. 1982. Together with Leptonema and Leptospira, Turneriella constitutes the family Leptospiraceae, within the order Spirochaetales. Here we describe the features of this free-living aerobic spirochete together with the complete genome sequence and annotation. This is the first complete genome sequence of a member of the genus Turneriella and the 13(th) member of the family Leptospiraceae for which a complete or draft genome sequence is now available. The 4,409,302 bp long genome with its 4,169 protein-coding and 45 RNA genes is part of the G enomic E ncyclopedia of Bacteria and Archaea project.

59 BASIC BIOLOGICAL SCIENCES↗
DOE OSTI2014

k-merSNP discovery: Software for alignment-and reference-free scalable SNP discovery, phylogenetics, and annotation for hundreds of microbial genomes

With the flood of whole genome finished and draft microbial sequences, we need faster, more scalable bioinformatics tools for sequence comparison. An algorithm is described to find single nucleotide polymorphisms (SNPs) in whole genome data. It scales to hundreds of bacterial or viral genomes, and can be used for finished and/or draft genomes available as unassembled contigs or raw, unassembled reads. The method is fast to compute, finding SNPs and building a SNP phylogeny in minutes to hours, depending on the size and diversity of the input sequences. The SNP-based trees that result are consistent with known taxonomy and trees determined in other studies. The approach we describe can handle many gigabases of sequence in a single run. The algorithm is based on k-mer analysis.

Source record↗
DOE OSTI2015

Barotrauma em peixes em usinas hidrelétricas: ferramentas para o estudo

The main source of electric power generation in Brazil comes from hydropower plants, nevertheless, the installed power is expected to raise 56.8%, reaching a total of 116,000 MW at the year 2020. The increase at the hydroelectric sector will be responsible for a series of fish community impacts. One of the impacts over the fish community is related to fish kills due to downstream passage through turbines or fish entrance at the draft tube from the tailrace. Usually when there is a maneuver and the turbine stops, fish get attracted and enter the draft tube and, just as the downstream passage through a turbine, when the turbine starts, a rapid decompression occurs and can cause barotrauma. When such events happen, according to Boyle’s law (P1V1=P2V2), swim bladder volume expands at the same rate that the pressure decreases, which can lead to the organ’s rupture.

barotrauma↗
DOE OSTI2016

Experimental Test Plan for PWR Sister Rods in the High Burnup Spent Fuel Data Project

The High Burnup Spent Fuel Data project pulled 25 sister rods (9 from the project assemblies and 16 from similar HBU assemblies) for characterization. The 25 sister rods are all high burnup and cover the range of modern domestic cladding alloys. The 25 sister rods were shipped to Oak Ridge National Laboratory (ORNL) in early 2016 for detailed non-destructive and destructive examination. Examinations are intended to provide baseline data on the initial physical state of the cladding and fuel prior to the loading, drying, and long-term dry storage process. Further examinations are focused on determining the effects of temperatures encountered during and following drying. Similar tests will be performed on rods taken from the project assemblies at the end of their long-term storage in a TN-32 dry storage cask (the cask rods ) to identify any significant changes in the fuel rods that may have occurred during the dry storage period. Additionally, some of the sister rods will be used for separate effects testing to expand the applicability of the project data to the fleet, and to address some of the data-related gaps associated with extended storage and subsequent transportation of high burnup fuel. A draft test plan is being developed that describes the experimental work to be conducted on the sister rods. This paper summarizes the draft test plan and necessary coordination activities for the multi-year experimental program to supply data relevant to the assessment of the safety of long-term storage followed by transportation of high burnup spent fuel.

dry storage↗
DOE OSTI2017

Passive filtration of air egressing from nuclear containment

A nuclear reactor includes a reactor core comprising fissile material disposed in a reactor pressure vessel. A radiological containment contains the nuclear reactor. A containment compartment contains the radiological containment. A heat sink includes a chimney configured to develop an upward-flowing draft in response to heated fluid flowing into a lower portion of the chimney. A fluid conduit is arranged to receive fluid from the containment compartment and to discharge into the chimney. A filter may be provided, with the fluid conduit including a first fluid conduit arranged to receive fluid from the containment compartment and to discharge into an inlet of the filter, and a second fluid conduit arranged to receive fluid from an outlet of the filter and to discharge into the chimney. As the draft is developed passively, there is no need for a blower or pump configured to move fluid through the fluid conduit.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2018

The 2018 Edition of the IRPhEP Handbook

The International Reactor Physics Experiment Evaluation Project (IRPhEP) was established to preserve and evaluate integral reactor physics experiment data, including separate or special effects measurements for nuclear energy and technology applications. Numerous international experiments have been performed over the past several decades to support reactor operations, safety, measurements, and design. Those experiments represent a significant investment of infrastructure, cost, and expertise that, in many instances, cannot be as easily reproduced. They represent valuable resources of data for present and future research, and provide the basis for recording, development, and validation of methods. Contributors worldwide collaborate to evaluate and review selected benchmark experiments for inclusion in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). Several new evaluations, and revisions to existing benchmarks have been prepared for inclusion in the 2018 edition of the IRPhEP Handbook. Additionally, an IRPhEP Uncertainty Guide was discussed to provide further guidance regarding the evaluation of reactor physics measurements besides criticality. Recent changes to the IRPhEP Handbook include five minor revisions, the revision of a previous benchmark evaluation to include new data, publication of a new draft benchmark evaluation, final approval for the formal publication of two formerly draft benchmark evaluations, and the inclusion of ten new benchmark evaluations. The IRPhEP Handbook now contains a total of 159 experimental measurement series from 54 unique reactor facilities. International participants are actively engaged in ongoing evaluation activities to prepare content for future editions of the IRPhEP Handbook. There are numerous experiment and reactor facilities worldwide from which benchmark data can be evaluated. Those interested in serving as evaluators and/or reviewers for the IRPhEP are encouraged to participate.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Policy, Regulatory, Legal, and Permitting Case Study Subtask 3.2 – Topical Report

This report summarizes the policy, regulatory, legal, and permitting requirements to-date for the siting of a CO 2 injection and storage project in the CarbonSAFE Illinois East Sub-Basin pre-feasibility study area. Where applicable, the East Sub-Basin case study focuses on a proposed carbon capture and storage (CCS) site location in West Terre Haute, Indiana. Indiana has established the legal mechanisms to obtain rights to the subsurface mineral estate with the expectation to apply to reservoir pore space for CO 2 storage in an analogous manner to storage of natural gas, which is a common practice in Indiana. There is, however, no precedent in Indiana to take liability for stored CO 2 . There are currently no Indiana State incentives for CCS, but at the Federal level, tax credits for carbon capture and storage under 26. U.S. Code § 45Q constitute the greatest incentive targeted at CCS projects. The amendment to these credits put forth in the Bipartisan Budget Act (the FUTURE Act) of 2018 substantially increases the per-ton incentive for CCS—from $22.66 per ton in tax year 2017 up to $50 per ton in tax year 2027, for CO 2 not used as an injectant (i.e. saline storage). Additional economic opportunities may exist for the provision of CO 2 for potential EOR in the Illinois Basin. Policies that may support the development of CO 2 pipelines and/or CCS projects in Indiana include: 1) Title 41 of the FAST Act (2015), which created a new governance structure, procedures, and funding authorities in order to improve and expedite Federal review and authorization of covered infrastructure projects, including pipelines, and 2) the Eminent Domain for Transportation of Carbon Dioxide by Pipeline (IC 14-39, Indiana State, 2011), which declares pipeline transportation of CO 2 exclusively to a carbon management application, including sequestration, enhanced oil recovery, and deep saline injection as a benefit to the welfare of Indiana and the people. The US Environmental Protection Agency’s (EPA) Underground Injection Control (UIC) Program Class VI rule and permit requirements address all components pertaining to CO 2 injection and monitoring for long-term storage, and outline the minimum technical criteria to protect underground sources of drinking water at, and surrounding, injection well sites. The Class VI requirements also address financial responsibility for corrective action, post-injection site care, and site closure. In addition, UIC Program public notice requirements include that the EPA issue notice of the draft permit preparation to key stakeholders, and open a public comment period of not less than 30 days. A public hearing about the permit would also be held, if specifically requested by the public. A potential Class VI CO 2 injection well permit for the East Sub-Basin case study site would be obtained through the US EPA Region 5, because the State of Indiana does not have UIC Class VI primacy. Although no CO 2 injection wells have been permitted in Indiana, the US EPA Region 5 (which covers Illinois and Indiana) and the East Sub-Basin CarbonSAFE team (via the Midwest Geological Sequestration Consortium [MGSC]) have Class VI permitting experience from several projects located in Illinois. Based on our experience, applying for a Class VI permit can be an intensive and iterative process requiring clear communication and numerous interactions with EPA staff. In addition to gathering and preparing the data/models and documentation necessary for a permit application’s initial submittal, the subsequent public comments, EPA response and review, and answering of any follow-up questions/requests by the EPA could significantly increase the timeframe of draft permit issuance. The US EPA offers guidance documents regarding the specific Class VI permit requirements, and shows a general permitting timeline example from the FutureGen Alliance 2.0 covering one-and-a-half years from permit submittal to issuance. However, the overall permitting process to-date has a high degree of variability, and in MGSC’s project experience we observed a more extended timeline to receive Class VI permits for each of two CO 2 injection wells.

01 COAL, LIGNITE, AND PEAT↗
DOE OSTI2019

The International Nuclear Material Transport Security Regime: A. Multi-Modal Tapestry of Conventions and Agreements

The international legal framework for transporting nuclear material is complex. The tapestry of conventions and agreements in place vary based on the material in transport, the mode or modes of transport used, and the location where the transport is taking place. The instruments range in scale from the international Convention on the Physical Protection of Nuclear Material and Nuclear Facilities and the Amendment to regional conventions and agreements such as those for rail transport (RID), inland waterway (ADN), and road (ADR). As part of their international commitments under the various conventions and agreements, signatories are required to abide by and harmonize their regulations to these international instruments. The challenge for Competent Authorities in drafting regulations consistent with a Member States obligation under international law can be complex. In addition to ensuring their own authority to draft regulations consistent with these conventions, a Competent Authority may need to coordinate with other ministries, departments, or agencies in mapping the various conventions, their annexes, the requirements therein, and understanding how to develop regulations that align both to international law and domestic law. This paper addresses each of these conventions and agreements; providing a summary description of what each means to individual entities that are transporting nuclear material, provide the total number of States Party to each, provide a graphical framework for unpacking the legal complexities at the international level to assist users and competent authorities in orienting themselves to the international instruments and how they apply to specific shipments. A detailed evaluation has been made of the various international and regional conventions and agreements that help govern the security during the international and in some cases the domestic transport of nuclear material, therein providing a tool for understanding the international transport regime for moving these materials.

Fialkoff, Marc↗
DOE OSTI2020

Regulatory Development Challenges and Opportunities for the Safe and Secure Transport of Radioactive Materials

Drafting regulations for transport safety and transport security achieve two separate objectives, which can lead to divergent outcomes. With transport safety, the principle goal is to protect the public and the environment from the effects of ionizing radiation, while in contrast, the principle goal of transport security is to protect the material from malicious actors. While many Member States may have transport safety regulations for radioactive materials, transport security regulatory development is still in its nascent stages globally. Trying to develop harmonized transport safety and transport security regulations could lead to challenges ranging from differences in terminology used in transport safety versus terminology uses in transport security, roles and responsibilities for the variety of stakeholders involved in transport, and finally, the possible role of multiple competent authorities in governing the transport of dangerous goods, which includes radioactive material. While the International Atomic Energy Agency (IAEA) is currently developing a process of a methodology for drafting transport security regulations, any process must address both safety considerations and security requirements. (As the most vulnerable part of the life cycle of radioactive materials, the need for harmonized transport safety/transport security regulations is essential.) This paper investigates the regulatory elements of the safety-security interface for nuclear and other radioactive material in transport. Examining challenges including use of terms, the role of multiple competent authorities, and practical challenges involved in the safe and secure transport of radioactive material, the paper analyzes the need for integrated regulatory development for the safe and secure transport of these materials.

Anderson, Kimberly↗
DOE OSTI2016

Modifications to the runner blade to Improve Off - Design Efficiencies of Hydraulic Turbines

Hydroturbines are known to have very high efficiency at their best efficiency point (BEP). However, it has become increasing beneficial to run some hydroturbines at conditions that are significantly different than BEP. This is a direct result of volatile price fluctuations on the electric market, limited storage capabilities, and environmental rules and regulations. Running the hydroturbine at off-design conditions can result in a significant amount of residual swirl in the draft tube. The presence of this residual swirl is particularly detrimental to the performance of Francis hydroturbines since they rely on a pressure head to generate power. Previous research at The Pennsylvania State University numerically discovered that injecting water through the trailing edge of the wicket gates could change the bulk flow direction upstream of the runner blades. In this manner, the flow rate and swirl angle entering the runner blade could be altered to limit residual swirl in the draft tube. The research determined that properly tuned jets could result in a significant improvement in turbine efficiency when the hydroturbine was operating at low flow. However, this required pumping water through channels into a region of relatively high pressure. This pump requirement lessened the effectiveness of the wicket gate trailing edge injection. The concept of water jet injection was further explored in the present work. However, instead of injecting water into a region of relatively high pressure, water jets were placed at the trailing edge of the runner blades where there is a region of relatively low pressure. It was determined that, although this water jet injection improved the off-design efficiency of a low flow case by 0.8%, the hydroturbine now required a larger head in order to maintain the flow rate. The present work found no increase in efficiency for the high flow case with the added water jet injection technique.

13 HYDRO ENERGY↗
DOE OSTI2021

Review of Graphite Properties Relevant to Micro-Reactor Design

Microreactors are advanced reactors that are designed to be small, scalable, and portable with up to 20 MW power. These reactors could operate independently, or as part of a microgrid, without need of a frequent refueling. Micro-reactors are designed to be deployable to provide electric power in remote locations, therefore providing greater flexibility. Several micro-reactors are under development in the US. These reactors are based on advanced gas-cooled or heat-pipe concepts. While Graphite can be found in various applications, some high-temperature reactors plan to employ Graphite in their core components due to its role as a moderator and its ability to maintain its structural integrity when subjected to elevated temperatures and high neutron fluence. Although there is significant experience with use of Graphite in nuclear applications, there are still unknowns that should be addressed. Graphite properties depend on the graphite type and affected by the fabrication procedures. Material properties are functions of the temperature and irradiation dose. The fundamental properties also affected by the oxidation environment. Therefore, in-depth understanding of graphite properties, including the effect of irradiation, oxidation and other influencing parameters are required to evaluate the design accurately. This draft aims to provide a comprehensive review of material properties for Graphite relevant to micro reactor design. For this work, two distinct grades of graphite were considered, namely IG-110 and Mersen-2114. Physical, thermal, and mechanical properties for these grades were comparatively evaluated. The properties that are discussed in this draft aim to serve as a basis for design and safety analysis.

42 ENGINEERING↗
DOE OSTI2020

ASME Code Activities

U.S. Nuclear Regulatory Commission (NRC) is currently assessing ASME Section III, Division 5 (2017 Edition) and accompanying Code Cases for endorsement Draft Regulatory Guide (DG-1380) and draft NUREG (2245) on the endorsement of Division 5 were issued and public comment phase completed DG-1380 places conditions in the areas of general requirements, mechanical design, metallic materials allowable stresses, and graphite materials/design of Division 5 DG-1380 is a revision to Regulatory Guide 1.87, Revision 1, 1975 (which endorsed the 159X series of ASME Code Cases, with conditions) NRC staff is currently reviewing the low-temperature and elevated temperature Alloy 617 code cases for endorsement Results of the review will be incorporated into DG-1380 and changes will be announced publicly The formal endorsement of Section III, Division 5 and accompanying code cases, with conditions, will be made through Regulatory Guide 1.87, Revision 2

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2013

NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely NRC's role will change from doing both consultation and monitoring to being focused on monitoring activities within NDAA. DOE has identified other activities at the Hanford Nuclear Reservation that would continue consultation activities but outside of the NDAA in the future. During the past seven years of consultations and monitoring a number of lessons learned about the process, communication issues, and technical guidance have been identified. With the change in focus from reviewing initial performance assessments and draft waste determinations to long-term monitoring (e.g., individual waste tank closure, at F Tank Farm or complete tank farm closure at INTEC expected in the near future), the NRC is going to revise and update its guidance over the next few years to reflect the lessons learned and the change in focus. In addition to the lessons learned, improvements in the guidance will have to account possible rule and guidance changes underway within Part 61. This paper will discuss the initial plans, approaches, and time lines to revise the guidance within NUREG-1854, including opportunities for public involvement. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Verification of the Accountability Method as a Means to Classify Radioactive Wastes Processed Using THOR Fluidized Bed Steam Reforming at the Studsvik Processing Facility in Erwin, Tennessee, USA - 13087

Studsviks' Processing Facility Erwin (SPFE) has been treating Low-Level Radioactive Waste using its patented THOR process for over 13 years. Studsvik has been mixing and processing wastes of the same waste classification but different chemical and isotopic characteristics for the full extent of this period as a general matter of operations. Studsvik utilizes the accountability method to track the movement of radionuclides from acceptance of waste, through processing, and finally in the classification of waste for disposal. Recently the NRC has proposed to revise the 1995 Branch Technical Position on Concentration Averaging and Encapsulation (1995 BTP on CA) with additional clarification (draft BTP on CA). The draft BTP on CA has paved the way for large scale blending of higher activity and lower activity waste to produce a single waste for the purpose of classification. With the onset of blending in the waste treatment industry, there is concern from the public and state regulators as to the robustness of the accountability method and the ability of processors to prevent the inclusion of hot spots in waste. To address these concerns and verify the accountability method as applied by the SPFE, as well as the SPFE's ability to control waste package classification, testing of actual waste packages was performed. Testing consisted of a comprehensive dose rate survey of a container of processed waste. Separately, the waste package was modeled chemically and radiologically. Comparing the observed and theoretical data demonstrated that actual dose rates were lower than, but consistent with, modeled dose rates. Moreover, the distribution of radioactivity confirms that the SPFE can produce a radiologically homogeneous waste form. The results of the study demonstrate: 1) the accountability method as applied by the SPFE is valid and produces expected results; 2) the SPFE can produce a radiologically homogeneous waste; and 3) the SPFE can effectively control the waste package classification. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255

The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sites and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct and install the necessary integrated systems to process the accumulated MVST Facilities SL inventory at the TWPC thus enabling safe and effective disposal of the waste. This BCP does not include work to support current MVST Facility Surveillance and Maintenance programs or the ORNL Building 3019 U-233 Disposition project, since they are not currently part of the TWPC prime contract. The purpose of the environmental compliance strategy is to identify the environmental permits and other required regulatory documents necessary for the construction and operation of the SL- PFB at the TWPC, Oak Ridge, TN. The permits and other regulatory documents identified are necessary to comply with the environmental laws and regulations of DOE Orders, and other requirements documented in the SL-PFB, Safety Design Strategy (SDS), SL-A-AD-002, R0 draft, and the Systems, Function and Requirements Document (SFRD), SL-X-AD-002, R1 draft. This compliance strategy is considered a 'living strategy' and it is anticipated that it will be revised as design progresses and more detail is known. The design basis on which this environmental permitting and compliance strategy is based is the Wastren Advantage, Inc., (WAI), TWPC, SL-PFB (WAI-BL-B.01.06) baseline. (authors)

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

Experimental test plan for PWR sister rods in the high burnup spent fuel data project

The High Burnup Spent Fuel Data Project (herein referred to as the 'project'), sponsored by the US Department of Energy (DOE) Office of Nuclear Energy (NE), is focused on experimentally defining the effects of long-term storage and transportation on high burnup (HBU) pressurized water reactor (PWR) fuel (>45 gigawatt days per metric ton uranium). The goals of the project are to provide confirmatory data for model validation and potential improvement; to provide input to future dry storage cask design; to support license renewals and new licenses for Independent Spent Fuel Storage Installation facilities; and to support transportation licensing for high burnup used fuel. In support of these project goals, an instrumented TN-32B bolted-lid cask at the North Anna reactor site will be loaded with intact, HBU PWR fuel assemblies (project assemblies) having four different kinds of cladding: standard Zircaloy-4, low-tin Zircaloy-4, ZIRLO, and M5. In approximately 10 years, the instrumented cask will be opened for inspection and several fuel rods from the project assemblies will be characterized. To support the project goals, the project pulled 25 'sister rods', 9 from the project assemblies and 16 from similar HBU assemblies, for characterization. The 25 sister rods are all high burnup and cover the range of cladding alloys. The 25 sister rods were shipped to Oak Ridge National Laboratory (ORNL) in early 2016 for detailed nondestructive and destructive examination. Examinations are intended to provide baseline data on the initial physical state of the cladding and fuel prior to the loading, drying, and long-term dry storage process. Further examinations are focused on determining the effects of temperatures encountered during and following drying. Similar tests will be performed on rods taken from the project assemblies at the end of the storage period (the 'cask rods') to identify any significant changes in the fuel rods that may have occurred during the dry storage period. Additionally, some of the sister rods will be used for separate effects testing to expand the applicability of the project data to the fleet, and to address some of the data-related gaps associated with extended storage and subsequent transportation of high burnup fuel. A draft test plan is being developed that describes the experimental work to be conducted on the sister rods. This paper summarizes the draft test plan and necessary coordination activities for the multi-year experimental program to supply data relevant to the assessment of the safety of long-term storage followed by transportation of high burnup used fuel. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗