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At least 1,099 records · Page 61

Distribution Grid Impact Study in Highland Park, Michigan: Understanding Rooftop Solar, Behind-the-Meter Energy Storage, Electric Vehicle Charging, and Building Electrification [Slides]

Through the Communities LEAP (Local Energy Action Program) Pilot, the National Renewable Energy Laboratory (NREL) engaged the Highland Park Stakeholder Coalition to scope four technical assistance work areas to address their energy needs and goals. This slide deck addresses the highlighted tasks under work area "B" related to policy analysis, due diligence, and case studies for removing barriers and providing best practices for local clean energy development. Highland Park community members face frequent, long-duration power interruptions due largely to the aging distribution system serving the area and the legacy design standards used in its construction. While degrading physical infrastructure such as poles, crossarms, and transformers can result in this substandard reliability, another notable characteristic of this legacy system is the lower, 4.8 kV, voltage class. This is a legacy construction standard which many utilities, DTE included, are phasing out in favor of higher, 15 or 25 kV, voltage classes instead. The existing 4.8 kV distribution system serving Highland Park may limit significant adoptions of clean-energy technologies like high percentages of building electrification or electric vehicle adoption. The following analysis seeks to quantify these limitations under a variety of clean-energy technology adoption scenarios. It compares the overall system risks of the present system to those of a hypothetical, upgraded 13.2 kV system, using NREL-developed risk metrics and offers upgrade cost considerations. The legacy 4.8 kV voltage class serving Highland park is not, as we have modeled it, a major limitation to the widespread adoption of cost-optimal rooftop solar and/or behind-the-meter energy storage. Within our modeling framework, these technologies namely impact secondary, low-voltage assets, which may be remedied without the need for a system-wide upgrade to a 13.2 kV voltage class. Our model of the current 4.8kV system indicates it is not capable of supporting community-wide electrification efforts. Widespread building electrification, and the resulting large increase in wintertime load, dramatically increases the prevalence of voltage violations and thermal overloading on the current 4.8 kV distribution system. These impacts illustrate the need for system-wide upgrades to a 13.2 kV voltage class to accommodate these technologies. Low to Moderate DER adoption does not adversely impact the grid but does improve undervoltage and asset overloading issues. However, these benefits are insufficient to defer grid upgrades. Higher DER penetration is shown to increase overvoltage and asset overloading in future electrification scenarios.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Scalable and Memory-Efficient Algorithms for Controlling Networked Epidemic Processes Using Multiplicative Weights Update Method

We study the problem of designing scalable algorithms to find effective intervention strategies for controlling stochastic epidemic processes on networks. This is a common problem arising in agent based models for epidemic spread. Previous approaches to this problem focus on either heuristics with no guarantees or approximation algorithms that scale only to networks corresponding to county-sized populations, typically, with less than a million nodes. In particular, the mathematical-programming based approaches need to solve the Linear Program (LP) relaxation of the problem using an LP solver, which restricts the scalability of this approach. In this work, we overcome this restriction by designing an algorithm that adapts the multiplicative weights update (MWU) framework, along with the sample average approximation (SAA) technique, to approximately solve the linear program (LP) relaxation for the problem. To scale this approach further, we provide a memory-efficient algorithm that enables scaling to large networks, corresponding to country-size populations, with over 300 million nodes and 30 billion edges. Furthermore, we show that this approach provides near-optimal solutions to the LP in practice.

Sambaturu, Prathyush↗

Sensitivity Analysis of Lbloca In Response To 10 Cfr50.46c New Rulemaking

The Nuclear Regulatory Commission (NRC) is proposing a new rulemaking on emergency core system/loss-of-coolant accident (LOCA) performance analysis. In the proposed rulemaking, designated as 10 CFR 50.46c, the US NRC puts forward an equivalent cladding oxidation criterion as a function of cladding pre-transient hydrogen content. The proposed rulemaking imposes more restrictive and burnupdependent cladding embrittlement criteria; consequently more fuel rods need to be analyzed under LOCA conditions to maintain the safety margin, in contrast to the current practice with which only one hot rod needs to be analyzed. New multi-physics analysis methods are required to provide a thorough characterization of the reactor core in order to identify the locations of the limiting rods and quantify safety margins under LOCA conditions. The U.S. DOE’s Light Water Reactor Sustainability (LWRS) Program has initiated a project to develop multi-physics analytical capabilities, called LOTUS, to support the industry in the transition to the proposed rule. An approach to uncertainty quantification and sensitivity analysis with LOTUS was developed. A typical four-loop PWR plant model was developed and simulated by RELAP5-3D with inputs generated from core design and fuel performance analyses, and uncertainty quantification and sensitivity analysis were performed with seventeen uncertain input parameters. The maximum equivalent cladding reacted ratio (ECRR) and peak clad temperature ratio (PCTR) were selected as the figures of merit (FOM). Pearson, Spearman, partial correlation coefficients, and Sobol indices were considered for all of the figures of merit in the sensitivity analysis.

10CFR50.46c↗

Fuel Refabrication Prototype - Presentation for 2021 ASI Annual Webinar

This power point presentation is a summary of the work produced in FY2021 under the LWR Fuel Reinstrumentation project funded by DOE's Advanced Sensor Initiative, and the outlook for FY22. The objective of this portion of the ASI program is to "Capture critical technology created by the Institute For Energy (formerly Halden Reactor Project) to reinstrument irradiated fuel rodlets, and further this technology to enable incorporation of advanced instrumentation: fiberoptics, LVDTs, ultrasonic based sensors". The presentation explains that two of the three equipment modules were received and INL and a number of practice runs were conducted with them. In FY22 the third equipment module will arrive and using the three equipment modules measurement sciences personnel will create a complete prototypical instrumented fuel rodlet (using ceramic surrogates in the place of UO2).

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Discussion on the merits of deep borehole disposal, especially with recycling - 15389

With the continued global expansion of the nuclear industry, disposal of spent nuclear fuel (SNF) and high level waste (HLW) continues to be a largely unimplemented (but extensively studied) activity throughout the world and can continue to do so due to the safe practices of 'interim' SNF/used nuclear fuel (UNF) and HLW storage. However as the industry continues to operate and expand in both existing and new countries, the accumulated SNF/UNF and HLW will continue to grow in both quantity and locations across the globe; hence, requiring more effort to control and monitor. Countries with nuclear power programs, or are considering starting nuclear power programs, must consider the potential financial and the engineering burden associated with both the interim storage and the disposal of SNF/UNF and HLW produced by these programs: can the cost of disposal be reasonably captured in the cost of electricity produced from nuclear programs and are there suitable sites for disposal in their country, such as a mined-geologic site, for the expected accumulated quantity of SNF and HLW? Answering these questions may be particularly vexing for countries with small nuclear programs where establishing viable disposal sites for SNF and HLW and funding of the development of these sites may be a challenge. In an effort to establish an alternative to traditional, expensive, mined-geologic disposal sites, the deep borehole option has been (re-)considered by multiple countries and entities to be a relatively simple solution to disposal of SNF and HLW. However, disposal of SNF in deep boreholes must overcome several issues including: (1) limiting-sized borehole diameters; (2) limited ability for retrieval; and (3) potential hang-up issues associated with lowering longer (e.g., > 180 inches) canisters down into a deep borehole. Since most SNF is a resource when recycled (i.e., UNF) and to dispose of it in an irretrievable manner would be wasteful, a more optimal alternative that could overcome these issues and maximize the benefits of the UNF is to recycle the UNF and dispose of the resulting HLW into deep boreholes. The multiple and mutual benefits of this approach are elucidated in this paper. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

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)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NFPA Distributed Energy Resources Safety Training (DERST) For Emergency Responders

The National Fire Protection Association, with support from the Department of Energy, executed a multi-year initiative to develop, enhance, and disseminate Distributed Energy Resources Safety Training (DERST) tools for U.S. emergency responders. As Distributed Energy Resources (DER)—such as solar photovoltaics, battery energy storage systems (ESS), electric vehicles (EVs), and associated infrastructure—become increasingly prevalent, the NFPA identified a critical need for up-to-date standardized, accessible, and effective safety training tailored for the fire service and related public safety professionals. The project delivered a comprehensive suite of educational resources to improve responders’ abilities to safely manage DER-related incidents. This included: • Revised Modular Training Courses: Updated classroom-based DER safety courses, now modular and accessible nationwide through fire academies and the North American Fire Training Directors (NAFTD) network. • Live Burn Testing & Research: A full-scale controlled burn of a DER-equipped residential structure provided real-world data and insights, forming the basis for updated best practices. • A Gamified Simulation Tool – Firefighters Incident Response Simulation Tool (FIRST): A first-of-its-kind, multiplayer, scenario-based simulation using the Unreal Engine 5.0 to train responders in a realistic virtual, multi-DER incident environment. • Field Familiarization Software Tools & Prop Guide: Digital DER field familiarization evolutions software guide and a prop development manual to support field-based DER training exercises, enhancing responders' hands-on familiarity with DER infrastructure and collaboration on virtual incident responses. • National Dissemination Strategy: Strategic partnerships with NAFTD, Vector Solutions, and others enabled wide-scale distribution, with over 5,000 departments accessing resources and 1,100+ departments adopting the simulator in the first seven months. Also provided a web portal for easy access to all training and simulation programs developed under this grant for the U.S. responder community. Key findings from the project—particularly from the burn test—led to paradigm shifts in fire response tactics. For example, traditional approaches to garage fires may be hazardous if DERs are present, due to explosive off gassing and thermal runaway risks. The new training emphasizes scene assessment, stand-off approaches, thermal imaging verification, and careful post-incident cooling of DER components to prevent reignition. This initiative has had a significant national impact, raising awareness, enhancing preparedness, and supporting safer DER incident response practices. Significant engagement from the media, public safety organizations, and PBS coverage has further amplified the reach and adoption of NFPA’s DER safety training, tools, and simulations.

14 SOLAR ENERGY↗

The CNSC's Inspector Training and Qualification Program and its Importance to the Nuclear Industry - 19370

Trained, qualified, and designated staff at the Canadian Nuclear Safety Commission (CNSC) conduct inspections of licensed nuclear sites as a method of compliance verification. This paper will describe the unique and comprehensive qualification process for CNSC inspectors, known as the Inspector Training and Qualification Program (ITQP). The ITQP includes service-line-specific training that is unique to each inspection group within the CNSC, dependent on the facility/industry type. The training requirements specific to staff in the Wastes and Decommissioning Division and its impact on safety at waste management sites across Canada will be discussed. This paper will specifically identify the importance of CNSC inspector training and detail how the unique training program requirements enable the CNSC to better identify and encourage compliance among nuclear waste and decommissioning sites in Canada. CNSC inspectors are designated under section 29 of the Nuclear Safety and Control Act (NSCA), and the powers of inspectors are outlined in section 32 of the NSCA. Having trained, qualified, and designated inspectors is paramount for both the CNSC and the nuclear industry. For the CNSC, this ensures that staff in the field are aware of potential hazards and how to mitigate such hazards (if applicable), that staff understand the regulatory framework and how to measure compliance against it, and that staff consistently apply CNSC values across the nuclear industry. For the industry, this ensures that staff present at nuclear facilities are knowledgeable and professional, that inspections are conducted in a consistent manner, and that any compliance actions issued are measurable and defendable against the regulatory framework. The CNSC's ITQP incorporates both theoretical (in-class and online) and practical training, and is broken down into six categories: mandatory training for all new employees; core training; service-line-specific training; on-the-job training; CNSC regulations training; and, recommended additional training. This paper will discuss in detail the specific aspects of each of these categories, the importance of each category including the difference between knowledge and skills acquired in theoretical versus hands-on training, and how CNSC staff in designated inspector positions (inspectors-in-training) progress through the program. The complete list of core training and service-line-specific training for inspectors in the Wastes and Decommissioning Division, including re-qualification requirements, will be explored throughout the paper. It is further important that CNSC designated inspectors undergo continuous learning to ensure that their skills remain up to date, as well as to ensure that inspectors requalify at defined intervals to enable the maintenance of the core knowledge and skills with which the determination of the person's qualification was based. The steps involved in this requalification process, as well as the importance of continuous learning and the maintenance of skills and knowledge will be further discussed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Pediatric dosing for locally acting drugs in submissions to the U.S. Food and Drug Administration between 2002 and 2020

Abstract Deriving pediatric doses for locally acting drugs (LADs) presents a unique challenge because limited systemic exposure hinders commonly used approaches such as pharmacokinetic matching to adults. This study systematically evaluated drug development practices used for pediatric dose selection of LADs approved by the U.S. Food and Drug Administration from 2002 to 2020. The three study objectives were: (1) to determine the dose selection approach for the labeled pediatric dose, (2) to examine the studied pediatric dose(s), and (3) to evaluate the characteristics of the pediatric clinical programs used to support the labeled pediatric dose. A total of 187 pediatric submissions were characterized for the labeled and studied pediatric doses of LADs. The pediatric dose was predominantly labeled as a flat dose (91%) and at a single‐dose level (67%) similar to adults. The majority (68.4%) of the submissions had the same labeled dose for pediatrics and adults. Independent pharmacodynamic/efficacy studies in pediatric patients commonly (64.2%) provided supportive evidence for the labeled pediatric dose. Inhalation, nasal, and injectable submissions had the highest number of clinical trials, lowest usage of an extrapolation of efficacy approach, and utilized diverse approaches in selecting the studied pediatric doses. This article highlights approaches for LAD dosing in pediatric patients and can be used to inform drug development of these products in the pediatric population.

Research & Experimental Medicine↗

Implementing Arbitrary/Common Concurrent Writes of CRCW PRAM

The Parallel Random Access Machines (PRAM) abstraction is the simplest and most elegant algorithmic model for the design and analysis of parallel algorithms. It consists of different models categorized based on the underlying memory access mode used, the most powerful of which is the Concurrent Read Concurrent Write (CRCW) model. A PRAM algorithm describes a series of rounds, each of which consists of a collection of operations that can be executed concurrently within the same time step. However, the lack of support for concurrent memory accesses and the prevalence of asynchronous programming models led to the belief that implementing CRCW PRAM algorithms is unattainable and prompted many to avoid this model except for theoretical studies of optimal performance.In this work, we study the arbitrary and common concurrent writes in the CRCW PRAM model and explore implementation challenges on general-purpose systems. Moreover, we examine current practices for implementing common/arbitrary concurrent writes and propose a new efficient lightweight and thread-safe method to implement concurrent writes through leveraging atomic instructions. To demonstrate the efficacy of our method, we developed OpenMP kernels for classical CRCW PRAM algorithms and provide experimental results and comparisons based on run time performance measured over the x86 multicore architecture. Our results show a performance speedup compared to current practices up to 4.5x across all our benchmarks.

Ghanim, Fady↗

Safety Case for Service Contracts

Safety cases developed for the Facilities Management and Operations Center (FMOC) are based on the requirements in MN471021, Work Planning and Control Criteria for Safe Design and Operations. The FMOC performs maintenance activities in various locations at Sandia National Laboratories, New Mexico (SNL/NM). SNL/NM consists of more than 6,000,000 square feet of buildings, structures, and site infrastructure on approximately 13,000 acres of land. The FMOC performs approximately 7500 service contract work orders a year to assist with operations and maintenance at the SNL/NM site and facilities. As part of the continual improvement process, this Safety Case will be reviewed and updated, as needed, or at a minimum every three years. People tend to underestimate the probability of an accident if none have occurred previously or if the person performing the work is skilled, and they tend to trust each other’s competence. Human error within systems must be identified and considered. The FMOC uses failure mode analysis (FMA) to determine how a system might fail and cause accidents, as well as the amount and types of controls needed. The FMOC includes interconnected elements, such as people, environment, procedures, facilities, equipment, and the hazards identified in the work analysis. A daily pre-task plan is required prior to any work activity. Changes in work practices will be communicated clearly to all service contractors and personnel by way of contractor pre-task planning, activity-specific plans, contract amendments, and/or training. The FMOC has created a safe-by-design intent approach for service contract execution starting at the planning stage and extending through the execution phase. The Safety Program (see Figure 2) summarizes how the FMOC connects work analysis elements with service contracts.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Better Buildings Alliance: 2013 Annual Report

We are pleased to share with you a copy of the 2013 Annual Report. Inside, you’ll find significant program accomplishments, profiles on highlighted members, and plans for 2014. With your contributions, support, and leadership over the past 12 months, the program has reached significant milestones, including: Growing membership to over 200 members, to represent over 10 billion square feet of U.S. commercial building space and one-seventh of the market; Increasing participation in the 15 Solutions Teams by 75%; Developing 3 new high-efficiency technology specifications that if widely implemented, could save more than $5 billion in energy costs per year; Launching the Advanced RTU Campaign and Wireless Meter Challenge, and surpassing 100 million sq. ft. in the Lighting Energy Efficiency in Parking (LEEP) Campaign; Welcoming partners in new sectors, including K-12 schools and local governments; The program is a critical element of the Better Buildings Initiative, driving 20% energy savings in the building sector by 2020 through innovation, new technologies, and profiling leadership. Thank you for your ongoing participation, we are looking forward to working with you in the new year on your energy saving targets and advancing technical and market practices that promote energy savings at your organization.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Annual Report, Fall 2016: Identifying Cost Effective Tank Waste Characterization Approaches

This report documents the activities that were performed during the second year of a project undertaken to improve the cost effectiveness and timeliness of SRNL’s tank closure characterization practices. The activities performed during the first year of the project were previously reported in SRNL-STI-2015-00144. The scope of the second year activities was divided into the following three primary tasks: 1) develop a technical basis and strategy for improving the cost effectiveness and schedule of SRNL’s tank closure characterization program; 2) initiate the design and assembly of a new waste removal system for improving the throughput and reducing the personnel dose associated with extraction chromatography radiochemical separations; and 3) develop and perform feasibility testing of three alternative radiochemical separation protocols holding promise for improving high resource demand/time consuming tank closure sample analysis methods.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Moving Beyond Bias

The benefits of diverse work groups have been well documented, and our leaders speak of the need for our laboratories to become more diverse and inclusive. Despite these motivators, the field of accelerator controls remains strikingly homogeneous. This trend continues despite many long standing programs to attract underrepresented groups to STEM careers and the explicit desire of leadership to create more inclusive organizations. Research consistently points to the strong role implicit bias plays in preventing organizations from truly providing equal opportunities. The desire to become more diverse must be coupled with a strong culture, cultivated to change deeply rooted practices which influence recruiting, hiring, development, and promotion decisions based on stereotypes rather than accomplishments and abilities. Real change in this arena requires intentional action across the board, not just from human resources and underrepresented groups. This paper discusses practical approaches to changing organizational culture to enable diverse work groups to grow and thrive.

White, Karen S.↗

Feasibility Study for Cathodic Protection of Waste Tanks at Hanford

The Hanford Nuclear Reservation site contains approximately 211 million liters of radioactive and chemically hazardous waste arising from nuclear weapons production, beginning with World War II, and continuing through the Cold War. The waste is stored in 177 carbon-steel underground storage tanks, of which 149 are single-shell tanks (SSTs) and the remaining are double-shell tanks (DSTs). The mission of an ongoing River Protection Project is to retrieve the waste from the underground storage tanks and then treat and immobilize (i.e., vitrify) it for disposal. Waste from the older SSTs is being progressively retrieved into the newer DSTs for storage pending treatment, immobilization, and disposal. Waste chemistry controls are in place to mitigate general corrosion, pitting corrosion, and stress corrosion cracking (SCC) and minimize corrosion risks to the carbon steel tank liners of DST at the Hanford Site. The chemistry control program focuses on preserving liner integrity while balancing the need for caustic/nitrite additions that have large downstream impacts on vitrification. Some of the DSTs store salt cake or sludge waste layers contain out-of-specification interstitial liquids that contact the primary tank bottom or sidewall. Remediation of such layers through chemical additions is not practical. At the present time, the most significant leak integrity concern at Hanford is for corrosion of the tank bottoms of DSTs where the solids layer is out of specification because of hydroxide ion depletion and consequently, pH values that are less than 12. Cathodic protection (CP) has been proposed as a possible way to protect the liners of such tanks against corrosion. The objective of this project was to investigate the feasibility of applying CP to Hanford DSTs to mitigate internal corrosion of the carbon steel tank primary liners. The scope of the project included (1) a literature review on the application of CP to storage tank systems, in general, and to waste tanks at the Savannah River Site (SRS) and Hanford, (2) a review of the finite element analysis (FEA) model recently developed to evaluate potentials for a DST, and (3) the development of a boundary element analysis (BEA) model for CP for a DST. Tank AN-107, one of the Hanford DSTs, was selected for this work because (1) the bottommost waste layer in the tank is out-of-specification, and (2) electrochemical and resistivity data, based on recent waste sampling and testing, are available for this tank. The overarching conclusion of this study is that, based on the available information, it is feasible to apply CP to mitigate internal corrosion of the primary liners of the Hanford DSTs. However, significant additional information and work are required before a CP system can be designed. Recommendations for next steps in the design of the CP system will be presented.

WIERSMA, BRUCE↗

Simple Wins: Driving Effective Implementation of Energy Efficiency Projects

Small- and medium-sized manufacturers (SMMs) in the United States, making up over 98% of manufacturing firms, account for 48.3% of the sector’s energy consumption. Despite access to energy assessments and technical resources, such as those from the US Department of Energy’s Better Plants program and Industrial Training and Assessment Centers, implementation rates for identified energy-saving measures remain lower than expectations, averaging 47%. Some barriers were identified by other researchers as limited workforce capacity, inadequate training, and time constraints hinder progress. This article studied the development of customized checklists together with the energy assessment report as a practical solution to improve implementation rates for energy efficiency projects among SMMs. The framework for the checklists was grounded in five principles: short, precise, actionable, relevant, and codeveloped (SPARC). A case study of a 500,000-squarefoot SMM demonstrates how tailored checklists targeting significant energy users—such as heating, ventilating and air conditioning (HVAC), lighting, and compressed air systems for this facility—can simplify the process for staff to do facility walkthroughs to monitor best practices and track the progress of energy efficiency project implementation.

Guo, Wei [Oak Ridge National Laboratory (ORNL), Oa↗

The BRIAR Dataset: A Comprehensive Whole-Body Biometric Recognition Benchmark at Extreme Distances and Altitudes (Collections 1-6)

The Biometric Recognition and Identification at Altitude and Range (BRIAR) program aims to extend biometric capabilities into severe operational environments characterized by long ranges, atmospheric turbulence, and elevated viewpoints. This paper introduces the program’s two final government collections expanding activities, environments, viewpoints, distances, and modalities, and adding appearance and environmental stressors. We refine curation/evaluation and include sequestered subsets to support controlled assessments. These updates strengthen BRIAR as a comprehensive resource for whole-body, face, and gait recognition at altitude and range, while maintaining privacy-first practices.

Yoon, Rocky [ORNL] (ORCID:0009000491499165)↗

Surrogate Models for TREAT Transient Calculations

The Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is currently preparing for resumption of operation after more than 20 years in a long-term standby state. In parallel with preparation for operations and a new transient testing program, the DOENE Advanced Modeling and Simulation program (NEAMS) has been supporting the development of three-dimensional transient multi-physics modeling capabilities within the reactor physics application MAMMOTH. Recently, the MAMMOTH reactor physics team has begun development of uncertainty and sensitivity analysis for the TREAT core. This research will be used to support the analysis of reactor operation and experiment planning. Traditional approaches, i.e., Monte Carlo simulations, for such tasks require a large number of model evaluations under both steady state and transient conditions. However, exhaustive sets of sampling runs are simply not practical for TREAT since evaluations of each model can take a substantial amount of time. A solution to this problem is to build a surrogate model employing a smaller number of model evaluations. The surrogate model is designed to provide an accurate and fast approximation to the detailed TREAT model. In this manner, the surrogate model can be used in place of the TREAT transient model for uncertainty and sensitivity analysis at a fraction of the computational cost. The high dimensional model representation (HDMR) method is employed here for approximating the responses of interest in terms of functions of lower dimensions. This method has been implemented in RAVEN and all TREAT transient calculations are performed using the multiphysics code MAMMOTH. In addition, a code interface has also been developed in order to couple RAVEN with MAMMOTH. The surrogate model is then tested and compared for TREAT startup testing program Transient Test no. 15 core, and its accuracy is measured by its ability to estimate the mean, coefficient of variance, skewness, excess kurtosis and probability density function of the outputs of Transient Test no. 15 model, as well as root mean square error metric.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗