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At least 1,279 records · Page 71

Laboratory Agenda 2018: Changing the world's energy future and securing our critical infrastructure

Idaho National Laboratory (INL) has a vision of changing the world’s energy future and securing our nation’s critical infrastructure. INL’s mission involves discovering, demonstrating, and securing innovative nuclear energy solutions and other clean energy sources. The Laboratory also has a mission focused on protecting the nation’s power grids and other vital systems against man-made and natural threats. Completing our mission and fulfilling our vision requires carefully charting our path and priorities, building and strengthening our core capabilities, focusing on key research and development (R&D) and mission-support initiatives, assessing our performance, and correcting our priorities when necessary. INL’s Laboratory Agenda articulates INL’s priorities, goals, and initiatives to deliver our mission and vision efficiently, effectively, and collaboratively. It describes our commitment to simultaneous excellence in science and technology, management and operations, and community service, and sets priorities for Laboratory investments.

99 GENERAL AND MISCELLANEOUS↗

Ten Principles for Power Sector Transformation in Emerging Economies

Access to reliable, affordable electricity is a key driver of economic growth in modern economies. The electric power sector, once a predictable and slow-moving industry, is now a complex system undergoing rapid transformation. Countries are in various stages of reforming and transforming their power sectors to better incorporate modern technologies, assure reliability and affordability, reduce harmful air emissions, meet a wide range of environmental goals, and achieve critical developmental objectives. This document offers action-oriented principles for emerging economy decision makers to consider while pursuing power system transformation (PST) pathways. They are organized into three categories: I. Foundations of Power System Transformation - important framework conditions for charting PST pathways; II. Accelerating Power System Transformation -- common strategies and approaches for accelerating PST efforts; and III. Moving Forward Inclusively with Power System Transformation -- considerations for fairness and equity in PST efforts.

24 POWER TRANSMISSION AND DISTRIBUTION↗

Final Results for 99 Mo, 111 Ag, 147 Nd, 140 Ba

Seven depleted uranium targets were irradiated at the ACRR reactor in three different irradiations occurring on June 4th, 5th, and 6th, 2019. The targets were received at LANL on July 10, 2019, unpackaged, and analyzed by autoradiography and gamma-ray spectrometry. Table 1 shows a chart of the Target ID, target mass, time the irradiation occurred, and the corresponding LANL sample ID. Six of the targets were dissolved and chemically separated radiochemical analyses were performed for a suite of radionuclides on four of the targets. The final results of the radiochemical separation and analysis of 99 Mo, 111 Ag, 147 Nd and 140 Ba for depleted U samples 4416-01, 4417-01, 4418-01 and 4418-03 are presented in Table 2. Associated errors represent 1σ uncertainty.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Ion-optical and Associated Magnet Feasibility Study of a High Rigidity Spectrometer

Ion-optical and magnet-feasibility studies were performed for the High Rigidity Spectrometer (HRS) at the Facility for Rare Isotope Beam (FRIB). The High Rigidity Spectrometer (HRS) will be the centerpiece experimental tool of the Facility for Rare-Isotope Beams (FRIB) fast-beam program The high magnetic rigidity of the HRS (8 Tm) will match the rigidities at which rare-isotope production yields at the FRIB fragment separator are maximum across the entire chart of nuclei and enable experiments with the most neutron-rich nuclei available at FRIB. Gain factors in luminosity of up to two orders of magnitude are achievable compared to running with existing spectrometers, which have a maximum rigidity of 4 Tm. The ion-optical studies were performed to ensure that the layout and properties meet the requirements for the scientific program envisioned for and articulated by the FRIB user community. Based on the ion-optical studies, magnet-feasibility studies were carried out to ensure that the magnets required for the HRS meet these requirements and can be constructed. The results of the ion-optical and magnet-feasibility studies form the basis of the pre-conceptual design for the HRS.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

FEEDER: Strategic Expansion to Achieve GEARED Goals (STEP)

This final report presents the summaries of the evaluation results and/or outcomes of the STEP program. This section presents the summaries of the evaluation results and/or outcomes of the STEP program. The evaluation metric results are shown in the charts below. For GEARED-wide evaluation results and a deeper discussion on the items presented here, please see the final report for award # DE-EE0007327.

99 GENERAL AND MISCELLANEOUS↗

Will Solar Panels Help When the Power Goes Out? Planning for PV Resilience

PV systems, like all energy systems, must chart a difficult course in order to improve resilience. They need to simultaneously withstand extreme conditions that cause grid power disruptions, be configured in a way that allows electricity to be delivered to meet the PV user's needs, and overcome disruptions arising from solar resource intermittency. Certain considerations reveal themselves as key to a PV system's resilience benefits. Choice of hardware is critical, as is site selection for the PV array. Voluminous evidence in a hurricane context demonstrates that durable hardware, properly maintained and sited, leads to PV systems surviving extreme weather with their functionality intact. Structurally weak or poorly maintained PV equipment, on the other hand, has demonstrated failures during extreme weather events. PV system stakeholders should ensure that best practices are followed for hardware procurement and siting. It is also important to understand that PV systems are not one-size-fits-all. While incorporating islanding capabilities and energy storage into the system's electrical topology will typically enhance resilience, the user's needs will determine the optimally resilient conformation of any given system. These factors - appropriate hardware, siting, maintenance, and system design - are the primary drivers of PV resilience. PV systems possess high potential for resilient energy generation due to their distributed, abundant, and free fuel supply, but the technology itself does not inherently lead to resilient outcomes. Realizing PV's potential for resilience requires consideration of these determinative factors.

14 SOLAR ENERGY↗

Equations of State in Computational Physics: What, Why, and How

Summary: 1. Equations of state furnish thermodynamic properties of a material. 2. Usually involve P, p (or V), and T, or P, r, and E 3. Necessary ingredient to solve compressible flow problems. 4. Varieties: i. Analytical expressions (ideal gas, Grüneisen) – fast, convenient for verification and test problems ii. Graphs and charts – good for hand calculations iii. Tables and databases – generally most accurate, require interpolation i. Steam tables ii. NIST database iii. SESAME EOS Library 5. Constructed by using semi-empirical models from Statistical Mechanics and fitting to available data

36 MATERIALS SCIENCE↗

AGR-1 Irradiated Compact 6-1-1 PIE Report: Evaluation of As-Irradiated Fuel Performance Using Leach Burn Leach, IMGA, Materialography, and X-ray Tomography

The AGR-1 irradiation test train consisted of six independently monitored capsules. All capsules contained twelve compacts in three stacks of four compacts each [Pope 2010]. Compact 6-1-1 was located in capsule 6, at the top of the test train. The compact was in stack 1 (one of the two stacks closest to the core) in position 1 (at the bottom of the 4 compact stack). Compact 6-1-1 was identified in the fabrication data package as LEU01-46T-Z32 [Hunn et al. 2006]. Details of the compact fabrication and measured properties can be found in that data package. The compact lot was made using TRISO-coated particles designated as AGR-1 Baseline fuel. These particles contained 19.7% enriched mixed uranium oxideuranium carbide (UCO) kernels with a O/U atomic ratio of ~1.36 and a C/U atomic ratio of ~0.33 [Pope 2010]. Details of the coated particle fabrication and measured properties can be found in the data package for the AGR-1 Baseline particles [Hunn and Lowden 2006]. The compact was irradiated at the INL Advanced Test Reactor (ATR) to an average calculated burn-up of 15.1% fissions per initial metal atom (FIMA) and an average calculated fast fluence of 3.0 x 10 25 n/m 2 [Sterbentz 2011] at a calculated volume averaged and time averaged temperature of approximately 1111°C [Hawkes 2012]. Capsules were disassembled and preliminary compact and graphite holder inspection was performed [Demkowicz et al. 2011]. Compact 6-1-1 was shipped to ORNL and post-irradiation examination (PIE) was performed according to examination plan PLN-3624 [Demkowicz 2010-2]. All the examination plan objectives listed below were completed except item 6, which was deleted due to limited funding. 1. Determine the inventory of fission products retained in the compact matrix, but not contained by the SiC and determine the number of exposed kernels or particles with defective SiC layers using the deconsolidation-leach-burn-leach method. 2. Gamma count all particles to quantify 137Cs inventory for comparison with calculated values and gamma spectrometric measurements made on the whole compact. Also, attempt to quantify the inventory of any other fission products for which gamma emissions are observed. 3. Characterize each particle based on the 137 Cs/ 144 Ce ratio to identify particles with low Cs retention that may be the result of a failed SiC coating. 4. Gamma count a subset of particles to determine the 110m Ag inventory for comparison with calculated values and gamma spectrometric measurements made on the whole compact. Also, attempt to quantify the inventory of other fission products observed. 5. Microscopically inspect selected particles to determine the condition of the kernels and coatings. This could include kernel migration, coating microstructures and defects, fission product attack of the SiC layer, and fission product migration in the coating layers. 6. Perform high temperature fission product release tests on a subset of particles in order to calibrate the collection efficiency of the Core Conduction Cooldown Test Facility (CCCTF) deposition cup for selected fission products. Gamma count particles before and after the heating test to quantify the released fission product fractions. 7. Archive remaining particles for later use. Compact 6-1-1 LBL began with compact deconsolidation in the Building 3525 hot cell, followed by two nitric acid leaches of the particles and matrix residue using a Soxhlet extraction apparatus. The matrix residue was then burned and the ash was leached twice with boiling nitric acid. The deconsolidated particles underwent an IMGA analysis to determine gamma-emitting isotope inventories for individual particles; the most conspicuous elements with reduced inventories, indicating fission product release, were silver and europium. During the IMGA analysis, particles with low silver were identified and a subset of these was set aside for materialography and x-ray. After the completion of the IMGA study, about 10% of the particles (421) were set aside as an archive and the remainder burned back and leached twice in the Soxhlet apparatus. Figure 1 shows a flow chart detailing the PIE of Compact 6-1-1.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Comparison between EMPIRE and TENDL

This report is a review of the proposed TENDL-2015 additions to the ENDF/B-VIII.0 library. We also discuss additions and modifications that are necessary so the new evaluations can be made usable. For that we performed calculations in the fast neutron range for the isotopes present in the TENDL- 2015 library as well as for other isotopes that either also satisfied the half-life criterion adopted by TENDL or filled the gaps between them in the nuclide chart. The quality of such calculations was assessed and compared to those of TENDL-2015, based on which recommendations were made. Finally, the files were validated so they can be incorporated into the ENDF/B-VIII.0 release.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Bioenergy Technologies Office 2019 R&D State of Technology

The U.S. Department of Energy’s Bioenergy Technologies Office funds research and development on technologies necessary for the deployment and production of cost-competitive bioenergy, primarily biofuels. Results of experimental efforts are periodically compiled and compared with benchmark technology designs to assess overall progress. This report provides a status of those R&D efforts at the end of 2019. This report first describes the approach for assessing progress followed by specific technology pathway configurations within which progress is charted. Each pathway configuration is described separately and the state of technology progress is presented for the combined pathway as well as for pathway components. Detailed component descriptions reference technology barriers and challenges that are detailed in the appendix.

09 BIOMASS FUELS↗

Substation Secondary Asset Health Monitoring and Management System (SSHM)

Electric Power Group, LLC (EPG) was awarded DOE OE0000850 to design, develop, and demonstrate a real-time software application for substation secondary equipment health monitoring and management at host utility American Electric Power (AEP), a cost share partner. This project addresses the need for monitoring substation equipment health and providing operators with tools to identify and take pre-emptive action to avoid catastrophic equipment failure. By monitoring synchrophasor data in real time, data anomalies that indicate potential asset failure can be detected and alerts can be sent to operators in time to take corrective actions. EPG developed two data driven algorithms to identify abnormal equipment signature patterns as well as a method using substation linear state estimation (SLSE). The software has been deployed on hardened PC’s and tested and validated for cost share partner AEP’s substations - 138kV and 765 kV. The SSHM software has been accepted by AEP and final demonstration of DOE - OE0000850 for AEP and DOE was successfully completed on March 17th, 2020. EPG developed the Substation Secondary Asset Health Monitoring (SSHM) Platform to analyze equipment failure signatures in PMU data and alert substation personnel when pre-emptive inspection, repairs and other actions are warranted to prevent potential catastrophic failures. This is the first system that automatically monitors the health of substation secondary assets and alerts users to emerging failures using synchrophasor measurements. SSHM uses high resolution PMU data from PTs, CTs, and CCVTs to analyze equipment signatures and identify anomalies that are precursor indicators of potential equipment failure. When an anomaly is detected, there is a likelihood of potential failure of monitored equipment, the system alerts the user with visual alarms including alarm trend charts and indicator lights on a oneline diagram of the substation.

24 POWER TRANSMISSION AND DISTRIBUTION↗

LDRD DR 20200022DR. First year Appraisal: A new era of nuclear physics at the electron-ion collider [PowerPoint]

The first year review of the project is presented, including the following topics: introduction of the EIC; project team and resources; project scope, science and outreach; feasibility review; minimal and stretch goals; organization chart - theory; summary of project deliverables met; detailed account of perturbative QCD accomplishments; and conclusions.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Integral Experiment Request 230 CED-3a (Summary Report)

During CED-3a, the following information is required, as specified in the April 1,2016 revision of the CEdT process manual: A detailed cost estimate; and, A resource loaded(baseline) schedule for execution of the experiment, data analysis, and publication. Appendix I is a Gantt chart or various phases of the project.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Monitoring Radiochemical Processing Streams for the 238 Pu Supply Program with Process Pulse II

Oak Ridge National Laboratory (ORNL) is developing advanced spectroscopic and real-time monitoring capabilities to improve the timeliness of analytical measurements and process decisions for the 238Pu Supply Program. Reducing the time, resources, and costs associated with each production campaign is critical because overlapping campaigns will be required to meet the production goals of the National Aeronautics and Space Administration. Real-time, in situ analytical measurements in the heavily shielded hot cells at the Radiochemical Engineering Development Center (REDC) will allow for rapid process information feedback and operational benefits that help the 238Pu supply program scale-up production efforts. Noteworthy steps were taken during Campaign 5 to establish the ability to monitor processing streams in real time with spectrophotometry and a commercially available online monitoring software called The Unscrambler X Process Pulse II (PP) multivariate statistical process monitoring system by Camo Analytics (version 5.60). PP automates univariate-type calculations within the software itself and executes multivariate models built using The Unscrambler X (version 10.4 or newer). The Unscrambler is a commercially available data analysis software made by the same company. PP is composed of easy-to-use-tools for all personnel, including data scientists and technicians. The software can be used to plot analyte concentration profiles, spectral data, and other process variables in real time. All process data are represented in a single view with interactive charts useful for viewing how a process evolves over time.

07 ISOTOPE AND RADIATION SOURCES↗

Roadmap for photovoltaic cyber security

Cyber-secure, resilient energy is paramount to the prosperity of the United States. As the experience and sophistication of cyber adversaries grow, so too must the US power system’s defenses, situational awareness, and response and recovery strategies. Traditionally, power systems were operated with dedicated communication channels to large generators and utility-owned assets but now there is greater reliance on photovoltaic (PV) systems to provide power generation. PV systems often communicate to utilities, aggregators, and other grid operators over the public internet so the power system attack surface has significantly expanded. At the same time, solar energy systems are equipped with a range of grid-support functions, that—if controlled or programmed improperly—present a risk of power system disturbances. This document is a five-year roadmap intended to chart a path for improving cyber security for communication-enabled PV systems with clear roles and responsibilities for government, standards development organizations, PV vendors, and grid operators.

24 POWER TRANSMISSION AND DISTRIBUTION↗

Aquifer Injection Modeling (AIM) Toolbox User Guide

The Aquifer Injection Modeling Toolbox (“AIM Toolbox”) software was developed by the Pacific Northwest National Laboratory (PNNL) for the U.S. Environmental Protection Agency’s (EPA) to provide a collection of analytical solutions suitable for evaluating the potential extent of the area impacted by subsurface injection operations. Subsurface injection operations are regulated under the EPA’s Underground Injection Control (UIC) program and are typically related to oil/gas development, waste disposal, or subsurface mining or storage. The analytical algorithms provided in the AIM Toolbox each have different approaches/assumptions/focus with respect to the nature and processes in subsurface and the nature of the injection operations. Collectively the set of analysis algorithms provides a broader evaluation of the area that can potentially be impacted by an injection operation. By providing estimates for the injectate plume extent, the software supports technical aspects of planning, evaluation, and overseeing injection activities. That is, the results help assess when further regulatory controls (e.g., monitoring, reporting) may be required and, in the case of disposal into an underground source of drinking water, the extent of the impacted area would require exemption from protection under the Safe Drinking Water Act. The AIM Toolbox software is available as a single-page web application, providing an interface to provide the necessary inputs, and both chart and map panes for visualizing the results. This User Guide describes the AIM Toolbox software, information required, user interactions, and the underlying basis of the calculations.

54 ENVIRONMENTAL SCIENCES↗

Global Trends of ASME "N-Stamp" Certifications for Nuclear Component Vendors

Historically, nuclear component manufacturing vendors, from small businesses through large conglomerates, have felt compelled to obtain an American Society for Mechanical Engineers (ASME) Nuclear Certification, known colloquially as an "N-stamp", to assure supply chain quality standards that will be acceptable to regulators and safety concerns. Since the N-stamp quality standard is a U.S.-origin code, combined with the apparent decline in the U.S. nuclear industry alongside the growth of the Asian nuclear industry, there is the question of whether the rest of the world, including new entrants to the nuclear industry, also regard N-stamp as a needed certification. This study addresses this question through analysis of the entire N-stamp database of holders, and former holders, of N-stamp certificates of all types and for all regions worldwide from 1989-2020 (the dates available in the database). From this 30 years of data, we find that actually U.S.-based vendors still consistently obtain the largest number of N-stamps worldwide over all time periods, but also find that the countries participating in the N-stamp certification process has broadly expanded beyond just North America, Japan, S. Korea and Western Europe (the primary N-stamp recipients before the mid-2000's). We produced global heats maps and bar charts to illustrate our findings, as well as further investigation into why the data shows changes over time and region. We note that nuclear entities involved with Soviet-type reactors do not participate in the N-stamp process, but instead pursue the Russian version PNAE, which is substantially similar to the ASME code. We conclude that at least from the N-stamp database, the United States nuclear component manufacturing industry is alive and well, although there have been some consolidations, and that the ASME N-stamp appears to still be a valued certificate worldwide, including in China which now ranks second only to the United States in obtaining N-stamp certificates in recent years. We further note that the vendors of new reactor types, in particular High Temperature Gas-Cooled Reactors (HTGRs) and Small Modular Reactors (SMRs), are actively engaged with ASME (and other U.S.-based nuclear standards bodies such as the American Nuclear Society and Nuclear Energy Institute) to coordinate updates to the ASME N-Stamp criteria to ensure applicability of the code for these new designs. Implications of these findings include the following: The global use of the U.S.-origin N-stamp certification supports the view that, despite the decline of the U.S. nuclear industry, the United States remains an esteemed global leader in the area of nuclear safety. As the U.S. Government works to revitalize the U.S. nuclear industry, especially in the area of exports, it may be beneficial to leverage the global standing of the N-stamp certification. The findings indicate that the N-stamp database would be a useful tool for the U.S. Government to use to track the growth of the civil nuclear industry in foreign countries, under certain circumstances. The Excel-format N-stamp database produced as part of this study may be a useful tool for this purpose. N-stamp data may be a useful tool for foreign governments to use to identify nuclear manufacturers within their own country, especially to identify "targets" for outreach on nuclear export control compliance. The U.S. Government could carry this message to foreign partners during bilateral engagements or as part of Nuclear Suppliers Group (NSG) discussions on industry outreach.

42 ENGINEERING↗