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At least 235 records · Page 13

Annual Summary Report for the Remote-Handled Low-Level Waste Disposal Facility—FY 2023

This Fiscal Year (FY) 2023 annual summary report (ASR) documents the continued adequacy of the performance assessment (PA), the composite analysis (CA) and associated operating disposal-authorization statement (ODAS) technical-basis documents for the Remote-Handled (RH) Low-Level Waste (LLW) Disposal Facility at Idaho National Laboratory. Annual review of the adequacy of the PA and CA for the RHLLW Disposal Facility ensures that conclusions of the analyses remain valid in accordance with requirements of Department of Energy (DOE) Order 435.1, “Radioactive Waste Management.” In FY 2023, no significant operational changes or other activities occurred that would cause deviation from the assumptions in the PA and CA pertaining to disposal geometry, verification of waste characteristics, tracking disposal inventories against total limits, facility-closure design, or institutional controls. Eleven waste canister shipments were received at the RHLLW Disposal Facility, and ten waste canisters were emplaced in disposal vaults.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NRC Reactor Operating Experience Analysis and Trend Summary: 2022 Update

This report presents a summary of the Nuclear Regulatory Commission (NRC) reactor operating experience analyses with data through 2022 as well as the reliability and frequency trends identified in the 2022 update reports for component performance study, loss of offsite power analysis, initiating events analysis, and system study provided on the NRC Reactor Operating Experience Results and Databases website (https://nrcoe.inl.gov/).

99 GENERAL AND MISCELLANEOUS↗

ORNL Peer Review Summary and Recommendations for: Advanced Reactor Designs Security Analysis, Risk, and Recommendations: Risks, Consequences, and Possible Design Mitigation Approaches Associated with Select Advanced Reactors Study

The purpose of this document is to provide a summary of the peer review conducted for the "Advanced Reactor Designs Security Analysis, Risk, and Recommendations: Risks, Consequences, and Possible Design Mitigation Approaches Associated with Select Advanced Reactors" study prepared by researchers at Idaho National Laboratory (INL), Argonne National Laboratory (ANL), and Oak Ridge National Laboratory (ORNL). The National Nuclear Security Administration (NNSA) International Nuclear Security (INS) program team requested that ORNL perform a peer review of the study report prior to publication as a final peer check before distributing the report to a broader audience.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Summary of Massachusetts Clean Energy Center's Workforce Needs Assessment for the City of Lawrence

In July 2023, the Massachusetts Clean Energy Center (MassCEC) published an employment report titled “Powering the Future: A Massachusetts Clean Energy Workforce Needs Assessment.” This report was intended to support the State in meeting its 2030 decarbonization goals by identifying both existing workforce and training resources as well as gaps and barriers that need to be addressed in order to scale the State’s workforce to meet future demand. The following is a summary of the content that is relevant to Lawrence, MA. This was completed as part of the US Department of Energy’s Communities LEAP (Local Energy Action Program) Pilot supporting the Lawrence Stakeholders Coalition (LSC) led by Browning the Green Space in partnership with Groundwork Lawrence, All In Energy, and the City of Lawrence.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Executive Summary of the Z Fundamental Science Program

The Z Fundamental Science (ZFS) Program is intended to provide access to the Z machine and its diagnostics for high energy density (HED) experiments in collaboration with a broad community of academic, industrial, and national laboratory research interests. ZFS experiments on the Z Facility focus on conducting fundamental research in HED science and help provide research experience necessary to maintain and grow the HED community, especially through involvement of researchers from academia. This report serves as an executive summary of the ZFS Program and provides a succinct synopsis of the history of the ZFS Program, metrics and impacts of the Program, as well as a brief list of the most impactful publications that have resulted from the various ZFS Projects relevant to laboratory astrophysics, plasma physics, and planetary physics.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

29 th International Training Course on the Physical Protection of Nuclear Materials and Nuclear Facilities (Project Summary)

Sandia National Laboratories (Sandia) has hosted the International Training Course on the Physical Protection of Nuclear Materials and Nuclear Facilities since 1978. This course is the flagship training course of the International Atomic Energy Agency (IAEA). On behalf of the National Nuclear Security Administration (NNSA), Sandia manages, develops, and coordinates all course materials, and works closely with the IAEA to arrange all logistical details for the course ITC-29 incorporated some updates to the facility models, based on feedback received in ITC-28 and the ITC-29 dry run. In addition, all the graphics were refreshed after ITC-28 and implemented in the posters, data handbooks, etc. As in ITC-28, the ITC-29 staff worked closely with the IAEA on course materials, including a peer review process to ensure all course materials were aligned with Nuclear Security Series No. 13 and other relevant international guidance documentation from the IAEA. Due to the COVID-19 pandemic, ITC-29 was postponed twice and eventually took place in the late summer/early fall of 2022. Due to ongoing COVID-19 restrictions and safety requirements, the number of participants was reduced by about 31 percent from 59 participants in ITC-28 to 41 in ITC-29. As a result, the number of subgroups also decreased from eight in ITC-28 to six for ITC-29. This enabled the Sandia team to implement more opportunities for social distancing, particularly in the large classrooms. Despite the challenges, ITC-29 still passed a significant milestone, with the one-thousandth participant of the international training course attending during this event. Finally, the ITC staff continued the use of its improved method of evaluation to capture participants’ satisfaction with the updated course and to gather feedback concerning future improvements. This document provides a brief description of ITC-29, including a summary of lessons learned and key recommendations for future development efforts.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Nuclear Material Control & Accounting for Pebble Bed Reactors (FY 2023 Summary Report)

This report discusses the work done under the US Department of Energy NE-5 Advanced Reactor Safeguards and Security Program during FY 2023. It provides a summary of material control and accounting (MC&A) for pebble bed reactors (PBRs) and addresses some of the main challenges with current PBR MC&A approaches that will inform safeguards and security by design efforts. The efforts to date have focused on tristructural isotropic (TRISO) pebble fuel material accounting and control including working with partners in industry, loss and production of nuclear material as part of reactor operations, burnup modeling and measurements, uncertainty quantifications for such modeling and measurements, statistical approaches needed, and measurement methods. The unique fuel management and utilization in a PBR, where the fuel in spherical form is introduced and circulates through the reactor, poses special challenges for MC&A. This contrasts with traditional water-cooled reactors in which the fuel is contained in large assemblies and can be easily identified and counted. Even online fueled reactors, such as the CANDU reactors (none of which operate in the United States), are significantly different because the fuel is still contained in relatively large assemblies, is uniquely identified, and the number of assemblies that pass through the core on an annual basis is much fewer than the hundreds of thousands that circulate in a PBR, none of which are uniquely identified. Additionally, the nature of the TRISO fuel results in very low heavy metal loading with each pebble containing less than 10 g of uranium and on the order of less than 1 g of fissile material. This low fuel density and the robustness of the TRISO particles are major features of the TRISO fuel from a safety basis as each TRISO particle and pebble acts as a containment for the nuclear material and fission products during normal and accident conditions. This also results in very low plutonium loading per pebble during normal operations, which is on the order of 0.1 g at full burnup. A major feature of PBRs is that they will allow for significantly higher burnup, on the order of 160 GWd/THM compared to the burnup of traditional LWRs, which is on the order of 45 GWd/THM. This is achieved by monitoring the pebbles as they circulate through the reactor and allowing them to be reintroduced into the core until the desired burnup is achieved and they are removed from the reactor and enter the spent fuel storage areas.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Summary Report of the Technical Meeting on International Network of Nuclear Reaction Data Centres IAEA Headquarters, Vienna, Austria

This report summarizes the IAEA Technical Meeting on the International Network of Nuclear Reaction Data Centres held at the IAEA Headquarters in Vienna, Austria from 14 to 17 May 2024. The meeting was attended by 26 participants representing 13 cooperative Centres from eight Member States (China, Hungary, India, Japan, Korea, Russia, Ukraine and USA) and two International Organisations (NEA, IAEA). A summary of the meeting is given in this report along with the conclusions and actions.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Pathways Analysis Summary: Decarbonization Potential for Industrial Subsectors - Preliminary Modeling Results

This provides a summary of draft modeling efforts undertaken by the U.S. Department of Energy (DOE) Industrial Efficiency and Decarbonization Office (IEDO) as an extension and expansion of the 2022 Industrial Decarbonization Roadmap. IEDO is providing these draft modeling results to support stakeholder engagement and inform office- and department wide strategy and decision making. Section 1 provides an overview of the context for this analysis and modeling as well as information on the decarbonization pillars characterized and the models themselves. Section 2 presents modeling results of one net-zero emissions pathway each for six industrial subsectors: cement, chemicals, food and beverage, iron and steel, petroleum refining, and pulp and paper. It is important to note that these pathways are just one example and there is no single pathway for any single industrial subsector. Competition across different possible pathways will be essential to industrial decarbonization success. Section 3 provides an overview of the “rest of industry” subsectors and a high-level overview of net-zero barriers, challenges, pathways, and technologies. IEDO will continue to consider net-zero pathways and modeling for these rest of industry subsectors. Additional details will be made available in the future on the IEDO website.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

A Summary of Advances in Document Summarization from 2023-2024

In computer science, Document Summarization is the task of condensing some quantity of text and related content through automated means. In this document, we review recent literature in text summarization. “Hybrid” extractive-abstractive approaches continue to be explored. Some of the latest efforts have also sought to enable users to adjust summaries with queries or other structure and begun to test reinforcement-learning style agentic LLM-based solutions.

97 MATHEMATICS AND COMPUTING↗

An Appraisal of the Performance and Characteristics of Summary Rays Calculated for the SALSA3D Traveltime Dataset

The SALSA3D tomographic model provides a crucial community resource for improving the quality (in terms of both accuracy and precision) of predictions of the traveltimes of seismic waves and therefore improving our ability to locate anthropogenic or natural seismic events. Constructing the requisite tomographic model requires addressing the challenges implied by a massive and growing dataset of traveltime measurements. This study explores one approach to tackle this challenge: the use of summary rays, which average traveltime measurements from sources within evenly spaced cells, thereby eliminating redundant data.

58 GEOSCIENCES↗

Power Technologies for Rail Decarbonization Workshop: Summary Report

Argonne National Laboratory organized the Power Technologies for Rail Decarbonization Workshop for the U.S. Department of Energy (DOE) Vehicle Technologies Office. The workshop offered an inclusive venue for different stakeholders to convey their perspective on challenges and opportunities in decarbonizing the rail sector. The first day of the workshop focused on (1) rail decarbonization efforts in the DOE and collaboration opportunities, (2) technology pathways to decarbonize rail, and (3) prime mover and low-carbon options for rail. The second day was devoted to (1) prime mover and zero-carbon options for rail, and (2) rail logistics, infrastructure, and safety. Each day raised challenges and solutions through presentations from national leaders and discussions among panel members and the audience. Through this engagement with different stakeholders, we will produce a cross-disciplinary recommendation for the role of government agencies to contribute meaningful research to address current technology gaps. The workshop included up 139 active participants and featured keynote speakers and panelists from Association of American Railroads, Progress Rail Locomotive, Wabtec, Burlington Northern Santa Fe Railroad, Amtrak, Caterpillar, Cummins, Renewable Energy Group-Chevron, DOE’s Bioenergy Technologies Office, California Air Resources Board, Federal Railroad Administration and multiple DOE national laboratories. This summary report presents highlights from participant discussions covering the topics of technology pathways to decarbonize rail, prime mover and low-carbon options, prime mover and zero-carbon options, as well as rail logistics, infrastructure, and safety. The variety of input gathered from the stakeholder attendees is vital, as it helps inform DOE on rail decarbonization challenges and opportunities. Stakeholder feedback is balanced against DOE strategic directions and priorities with consideration of the roles of government and industry.

33 ADVANCED PROPULSION SYSTEMS↗

Summary of Expansions and Updates in R&D GREET® 2024 Rev.1

The research and development (R&D) version of Greenhouse gases, Regulated Emissions, and Energy use in Technologies (GREET®) model, or R&D GREET, is developed by Argonne National Laboratory (Argonne) with the support of the U.S. Department of Energy (DOE) and other federal agencies. R&D GREET is a life cycle analysis (LCA) model, structured to systematically examine the energy and environmental effects of a wide variety of transportation fuels and vehicle technologies in major transportation sectors (i.e., road, air, marine, and rail) and other end-use sectors, and energy technology systems. Argonne has expanded and updated the model in several areas in R&D GREET 2024 Rev.1. This report provides a summary of the expansions and updates.

54 ENVIRONMENTAL SCIENCES↗

El Capitan System Readiness: L2 Milestone Summary

This document is the written summary for the El Capitan System Readiness CSSE L2 Milestone from Lawrence Livermore National Laboratory. It briefly summarizes the efforts involved in preparing the El Capitan supercomputer for the local compute environment, and it describes how those efforts fulfill the requirements of ASC L2 #9235.

97 MATHEMATICS AND COMPUTING↗

Monitoring L2 Milestone Summary: Converged HPC Center-Wide Data Analytics

This document is the summary for the ASC 2025 L2 milestone Converged HPC Center-Wide Data Analytics. It describes the convergence of the center-wide monitoring at LC, the data sources involved, and different ways this has enabled analyzing and gaining insights from the data.

97 MATHEMATICS AND COMPUTING↗

TA-54 Flanged Tritium Waste Container Operations, Radioactive Air Emissions Summary Volume 1: Stack Emissions & Off-Site Dose Consequence

In September 2025, pressure mitigation operations began on the four Flanged Tritium Waste Containers (FTWCs) that had been in storage at Los Alamos National Laboratory (LANL), Technical Area (TA-) 54, Area G, Building 1028. Each FTWC was opened at TA-54 and put into a stable configuration, then containers were moved to LANL’s Weapons Engineering Tritium Facility (WETF) for further processing in preparation for shipment off-site. Over the course of 13 operational days, the project had air emissions of 123 curies of tritium (hydrogen-3). The radiological dose to the hypothetical maximally exposed individual (MEI) member of the public from these emissions was 0.012 millirem. This is well within the limits established by the Environmental Protection Agency (EPA), which allows 10 millirem per year to any member of the public. Naturally occurring background radiation in Northern New Mexico averages about 300-400 millirem per year to residents. This report is intended to briefly summarize operations that took place in September and October 2025, provide documentation of the radionuclide air emissions from these operations, and summarize the off-site dose consequence to the public that resulted from these air emissions. Informal notifications addressing these areas were made via email to the EPA and NMED throughout the project, and summaries of these data were also posted on the LANL external web site 1 for FTWC operations.

54 ENVIRONMENTAL SCIENCES↗