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At least 1,585 records · Page 88

Compact mobile-reader system for two-way wireless communication, tracking and status monitoring for transport safety and security

A system for monitoring a plurality radio frequency identification tags is described. The system uses at least one set of radio frequency identification tags. Each tag is attached to a container and includes several sensors for detecting physical conditions of said container. The system includes at least one autonomous intermediate reader in wireless communication with the frequency identification tags. The intermediate reader includes external wireless communication system, intermediate reader logic controller, and a self-contained rechargeable power supply. The system uses a central status reporting system in communication the intermediate reader.

97 MATHEMATICS AND COMPUTING↗

CoMET Project Status and Accomplishments

FY2020 status report on the 'Combined Materials Experiment Toolkit (CoMET)' software application for the annual program review of the Nuclear Science User Facilities.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Current Status of the DOE/NNSA Nuclear Criticality Safety Program Hands-On Criticality Safety Training

The U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA) Nuclear Criticality Safety Program (NCSP) has conducted two-week Nuclear Criticality Safety (NCS) Practitioner courses since 2011 to support the training and qualification of new NCS staff. The course was developed in accordance with the American National Standard Institute/American Nuclear Society (ANSI/ANS) standard for NCS training and qualifications (ANSI/ANS-8.26-2007). In 2013, an NCS Manager’s course was developed for process supervisors, managers, regulators, and other professionals with NCS-related responsibilities. This course was revised in 2019 for Criticality Safety Officers (CSOs) based on an NCSP Criticality Safety Support Group tasking (2018-01). This course was piloted at the Nevada Field Office and the National Criticality Experiments Research Center (NCERC) in June 2021. These courses consist of the following training components: classroom education, facility training, and hands-on subcritical and critical experiments training. The two-week Practitioner course offers a week of classroom training, with practical workshops and exercises focused on teaching students how to perform an NCS evaluation. The second week of training involves hands-on critical and subcritical experiments and measurements. The first week is offered in Las Vegas, Nevada, at the DOE Nevada Field Office or the National Atomic Testing Museum. Depending on the student’s clearance level, the second week is offered at Sandia National Laboratory (SNL) (uncleared and L-cleared students) or at the National Criticality Experiments Research Center (Q-cleared students). The one-week Manager’s course is offered at SNL or NCERC, depending on clearance or interest, and includes classroom and hands- on critical and subcritical experiments and measurements. This paper provides an overview and status report for the DOE/NNSA NCSP training courses in NCS and to provide information about future course offerings. This paper discusses the challenges associated with executing the training courses during the COVID-19 pandemic. The 2-week Practitioner and 1-week manager courses are currently offered twice per year and adjustments are made based upon demand.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Domestic and International Standards for Nuclear Criticality Safety – Overview and Status

The domestic and international consensus standards for nuclear criticality safety (NCS) have provided guidance for staff performing hands-on work in operations with fissionable materials. These consensus standards have contributed directly to the significant reduction in the rate of criticality accidents in process facilities since the 1940s. The last known criticality accident inside the United States was in 1978 (nearly 43 years ago) at the Idaho Chemical Processing Plant, and outside the United States, an accident occurred at Tokai-mura, Japan, in 1999 (23 years ago). The domestic consensus standards for NCS include the American Nuclear Society (ANS) standards. The ANS Standards Board, the NCS Consensus Committee, and the ANS-8 Subcommittee oversee the development and maintenance of these standards. There are currently eighteen standards in the ANS-8 series. Currently, there are six ANS-8 standards in revision mode and eleven in a maintenance mode with one new standard under development. The international consensus standards for NCS calculations, procedures, and practices are maintained and developed within the International Organization for Standardization (ISO), Technical Committee 85 on Nuclear Energy, Subcommittee 5 on Nuclear Fuel Technology, and Working Group 8, “Nuclear Criticality Safety.” Eleven standards are currently available, three standards are in revision mode, and two standards are development. This paper provides the NCS community with an overview and status report of domestic and international NCS consensus standards to stimulate interest and to support their continued development.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Domestic and International Standards for Nuclear Criticality Safety - Overview & Status [Abstract]

The domestic and international consensus standards for nuclear criticality safety (NCS) have provided guidance for staff performing hands-on work in operations with fissionable materials. These consensus standards have contributed directly to the significant reduction in the rate of criticality accidents in process facilities since the 1940s. The last known criticality accident inside the United States was in 1978 (nearly 43 years ago) at the Idaho Chemical Processing Plant, and outside the United States, an accident occurred at Tokai-mura, Japan, in 1999 (22 years ago). The domestic consensus standards for NCS include the American Nuclear Society (ANS) standards. The ANS Standards Board, the NCS Consensus Committee, and the ANS-8 Subcommittee oversee the development and maintenance of these standards. There are currently eighteen standards in the ANS-8 series. Currently, there are six ANS-8 standards in re- vision mode and eleven in a maintenance mode with one new standard under development. The international consensus standards for NCS calculations, procedures, and practices are maintained and developed within the International Organization for Standardization, Technical Committee 85 on Nuclear Energy, Subcommittee 5 on Nuclear Fuel Technology, and Working Group 8, “Nuclear Criticality Safety.” Eleven standards are currently available, three standards are in revision mode, and two standards are development. This paper provides the NCS community with an overview and status report of domestic and international NCS consensus standards to stimulate interest and to support their continued development.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Current Status of the DOE/NNSA Nuclear Criticality Safety Program Hands-On Criticality Safety Training [Abstract]

The U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA) Nuclear Criticality Safety Program (NCSP) has conducted two-week Nuclear Criticality Safety (NCS) Practitioner courses since 2011 to support the training and qualification of new NCS staff. The course was developed in accordance with the American National Standard Institute/American Nuclear Society (ANSI/ANS) standard for NCS training and qualifications (ANSI/ANS-8.26-2007). In 2013, an NCS Manager’s course was developed for process supervisors, managers, regulators, and other professionals with NCS-related responsibilities. This course was revised in 2019 for Criticality Safety Officers (CSOs) based on an NCSP Criticality Safety Support Group tasking (2018-01). This course was piloted at the Nevada Field Office and the National Criticality Experiments Research Center (NCERC) in June 2021. These courses consist of the following training components: classroom education, facility training, and hands-on subcritical and critical experiments training. The two-week Practitioner course offers a week of classroom training, with practical workshops and exercises focused on teaching students how to perform an NCS evaluation. The second week of training involves hands-on critical and subcritical experiments and measurements. The first week is offered in Las Vegas, Nevada, at the DOE Nevada Field Office or the National Atomic Testing Museum. Depending on the student’s clearance level, the second week is offered at Sandia National Laboratory (SNL) (uncleared and L-cleared students) or at the National Criticality Experiments Research Center (Q-cleared students). The one-week Manager’s course is offered at SNL or NCERC, depending on clearance or interest, and includes classroom and hands-on critical and subcritical experiments and measurements. This paper provides an overview and status report for the DOE/NNSA NCSP training courses in NCS and to provide information about future course offerings. This paper will also discuss the challenges associated with executing the training courses during the COVID-19 pandemic. The 2-week Practitioner and 1-week manager courses are currently offered twice per year and adjustments are made based upon demand.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Current status of the DOE/NNSA nuclear criticality safety program hands-on criticality safety training courses

In 2011 the US Department of Energy/National Nuclear Security Administration (DOE/NNSA) Nuclear Criticality Safety Program (NCSP) developed and piloted a 2-week nuclear criticality safety (NCS) practitioner course to support training and qualification of new NCS staff. The course was developed in accordance with the American National Standard Institute/American Nuclear Society (ANSI/ANS) standard for NCS training and qualifications (ANSI/ANS-8.26-2007). In 2013, an NCS manager's course was developed for process supervisors, managers, regulators, and other professionals with NCS-related responsibilities. These courses consist of classroom education, facility training, and hands-on subcritical and critical experiments training. Each course is currently offered twice per year. The 2-week practitioner course offers a week of classroom training, with practical workshops and exercises focused on teaching students how to perform an NCS evaluation. The second week of training involves hands-on critical and subcritical experiments and measurements. The first week is offered in Las Vegas, Nevada, at the DOE Nevada Field Office or the National Atomic Testing Museum. Depending on the student's clearance level, the second week is offered at Sandia National Laboratory (SNL) (uncleared and L-cleared students) or at the National Criticality Experiments Research Center (NCERC) (Q-cleared students). The 1-week manager's course is offered at SNL or NCERC, depending on clearance or interest, and includes classroom and hands-on critical and subcritical experiments and measurements. This paper provides an overview and status report for the DOE/NNSA NCSP training courses in NCS and provides information about future course offerings. (author)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Overview and status of domestic and international standards for nuclear criticality safety

For many years, the domestic and international consensus standards for nuclear criticality safety (NCS) have provided guidance for those performing hands-on operations involving fissionable materials. These consensus standards have been crucial to reducing the number of criticality accidents in process facilities. The last known criticality accident inside the United States was in 1978 (39 years ago at this writing) at the Idaho Chemical Processing Plant, and outside the United States, an accident occurred at Tokai-Mura, Japan, in 1999 (18 years ago at this writing). The domestic consensus standards for NCS include the American Nuclear Society (ANS) standards. The ANS Standards Board, the NCS Consensus Committee, and the ANS-8 Subcommittee oversee the development and maintenance of these standards. There are currently eighteen standards in revision (seven) or maintenance (eleven) cycles, and one standard is currently in development. The international consensus standards for NCS calculations, procedures, and practices are maintained and developed within the International Organization for Standardization, Technical Committee 85 on Nuclear Energy, Subcommittee 5 on Nuclear Fuel Technology, and Working Group 8, Nuclear Criticality Safety. Seven standards are currently available, one standard is in revision, and four standards are at various stages of development. This paper provides the NCS community with an overview and status report of domestic and international NCS consensus standards to stimulate interest and to support their continued development. (author)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Preliminary Flattop-25 Reevaluation Results

This paper is a preliminary status report on a reevaluation of the Flattop-25 criticality benchmark that is under way. Flattop-25 consists of a nearly spherical oralloy (Oy) core reflected by a nearly spherical tuballoy (Tu) or natural uranium reflector. In the International Criticality Safety Benchmark Evaluation Project (ICSBEP), the Flattop-25 benchmark is HEU-METFAST- 028 Rev. 1. A simplified one-dimensional spherical version of Flattop-25 was given in LA-4208 in 1969. The handbook evaluation presented the LA- 4208 model with material definitions slightly modified from the Cross Section Evaluation Working Group (CSEWG) benchmark. The reevaluation will include a detailed three-dimensional model of a specific Flattop-25 configuration. The k{sub eff} calculated using MCNP6 for the preliminary Flattop-25 detailed three-dimensional benchmark model is 0.00632 larger than the measured k{sub eff}. The preliminary uncertainty is ±0.00157, and the uncertainty in the uncertainty is estimated to be +100%/-0%. The largest driver of the k{sub eff} uncertainty and its uncertainty is the uncertain mass and density of the Tu reflector parts. Validating the geometry and mass of the Tu reflector parts is work for the near future. The benchmark model uranium part masses are generally going to be smaller than those in the preliminary model, but we do not yet know how much smaller. (author)

42 ENGINEERING↗

Borehole Disposal: Update on the Science, Technology, and Potentially Suitable Radioactive Wastes - 20170

A recent Special Issue of the Energies Journal on Deep Borehole Disposal of Nuclear Waste has delivered a timely update on the science and technology of borehole disposal and the types of radioactive wastes it could potentially accommodate. The Special Issue papers discuss (i) circumstances under which a national waste management programme might wish to consider deep borehole disposal [1], (ii) a status report of deep borehole disposal options in Germany [2], (iii) the use of deep horizontal drill-holes in sedimentary, metamorphic or igneous rocks for disposal of spent nuclear fuel and high-level radioactive waste [3], (iv) the analysis of corrosion performance of engineered barrier systems [4], (v) a review of the potential cementing systems suitable for deep borehole disposal [5], (vi) the thermal evolution around heat-generating waste for a wide range of material properties and disposal configurations [6], (vii) a geochemical analysis of deep brines focussed on fluid-rock interactions [7], (viii) post-closure performance assessment calculations for deep borehole disposal of Cs/Sr capsules [8], and (ix) an example safety case for deep borehole disposal of nuclear wastes [9]. This paper provides an overview of the main findings from these publications and highlights some of the technological and scientific challenges that need to be overcome when developing a deep borehole disposal concept. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The conduct of the united states department of energy nuclear criticality safety program hands-on training and education courses - 14621

The United States Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP), funded and managed by the National Nuclear Security Administration (NNSA), offers courses to educate nuclear criticality safety (NCS) engineers, process supervisors, and others, and to provide experimental, hands-on training addressing important characteristics of neutron multiplying systems. This training satisfies the American National Standard Institute/American Nuclear Society (ANSI/ANS)-8.26-2007 requirement for participating in hands-on experiments with fissionable materials and provides awareness and understanding of DOE Orders, Guides and Rules, ANS standards, and hazard identification techniques, as well as control design, implementation, and maintenance in criticality safety evaluations. Since the pilot course was developed in 2011, a variety of courses have been developed for NCS practitioners and process supervisors. Attendees have come from several US and international sites. Through NCSP international collaborations and relationships, students from the Atomic Weapons Establishment (AWE) in the United Kingdom, Atomic Energy of Canada, and the Institute for Radiation Protection and Nuclear Safety in France have participated in these courses in the US. Manager courses are available for process supervisors and operations managers with NCS responsibilities in their daily jobs. Manager courses are taught at Sandia National Laboratory (SNL) and the National Criticality Experiments Research Center (NCERC); they offer a combination of hands-on experiments and classroom discussions. A two-week course is also offered for NCS practitioners, with a week of classroom instruction at Los Alamos National Laboratory (LANL) focused on generation of NCS evaluations, and a week of hands-on training utilizing the critical assemblies at either SNL or NCERC. Cleared students can attend the hands-on training at either SNL or NCERC, and uncleared students can attend at SNL. Courses continue to evolve and continuously improve as important elements of NCS evaluations (e.g., human factors, non-destructive assay (NDA) techniques, process criticality accident lessons-learned, and hand calculation methods) are integrated with criticality safety evaluation exercises. Courses include tours of process operations at SNL, NCERC, and LANL, and interaction with instructors experienced in conducting critical experiments and working in NCS. The NNSA NCSP provides management, funding, and technical direction for these courses and makes them available with no tuition cost to NCS practitioners. This paper provides a status report to the NCS community on the conduct of these courses and how they will likely evolve in the future. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Study of neutron beta decay with the Nab experiment

The current three sigma tension in the unitarity test of the Cabbibo-Kobayashi-Maskawa (CKM) matrix is a notable problem with the Standard Model of elementary particle physics. A long-standing goal of the study of free neutron beta decay is to better determine the CKM element Vud through measurements of the neutron lifetime and a decay correlation parameter. The Nab collaboration intends to measure a, the neutrino-electron correlation, with accuracy sufficient for a competitive evaluation of Vud based on neutron decay data alone. This paper gives a status report and an outlook.

Baessler, Stefan↗

Domestic and International Consensus Standards for Nuclear Criticality Safety - Overview & Status

The domestic and international consensus standards for nuclear criticality safety (NCS) were developed based on the lessons-learned from process criticality accidents. These consensus standards were developed to reduce the rate of process criticality accidents in facilities that process, store, handle, or transport fissionable materials by hand. After a significant increase in criticality accidents through the mid-1960s, the rate of criticality accidents decreased as a result of these standards, and the criticality accident rate is extremely low from an industrial safety perspective. The last known criticality accident inside the United States was in 1978 (nearly 47 years ago) at the Idaho Chemical Processing Plant, and outside the United States, an accident occurred at Tokai-mura, Japan, in 1999 (almost 26 years ago). The domestic consensus standards for NCS include the American National Standards (ANS) that are prepared and published by the American Nuclear Society and approved by the American National Standards Institute (ANSI). The ANS Standards Board, the NCS Consensus Committee, and the ANS-8 Subcommittee oversee the development and maintenance of these standards. There are currently 18 standards in the ANS-8 series. Nine ANS-8 standards are either in revision mode or planned for revision. A new standard for the use of nondestructive assay measurements (ANSI/ANS-8.28-2024) for NCS was approved in March of 2024. The international consensus standards for NCS calculations, procedures, and practices are maintained and developed within the International Organization for Standardization, Technical Committee 85 “Nuclear Energy,” Subcommittee 5, “Nuclear Fuel Technology,” and Working Group 8, “Nuclear Criticality Safety.” Eleven standards are currently available, four standards are proposed for revision, and four standards are at various stages of development. This paper provides the NCS community with a high-level overview and status report of domestic and international NCS consensus standards to stimulate interest and to support their continued development.

Bowen, Douglas G [ORNL] (ORCID:0000000212460026)↗

Controls Status of Fermilab's PIP-II Project

The Fermilab Proton Improvement Project II (PIP-II) is building a new Super Conducting Linear Accelerator (SCL) accelerating protons to 800 MeV for injection into the rest of the FNAL beam complex. Key progress since the last status report given at ICALEPCS includes the adoption of modern DevOps practices with continuous integration and GitOps-based deployments, commissioning of EPICS-based systems at the Cryomodule Test Facility, and integration of a Virtual Accelerator framework for application development ahead of installation. In parallel, web-based applications using Dart and Flutter have matured, providing secure, unified access to both EPICS and legacy ACNET data. Data acquisition and timing systems have also evolved. This paper presents the current state of controls, emphasizing these recent developments and outlining upcoming milestones as PIP-II approaches commissioning of its cryoplant in 2026 and the Warm Front End in 2027.

Crisp, D. B. [Fermilab]↗

IEA Bioenergy Countries' Report: Bioenergy policies and status of implementation

This report was prepared from IEA statistical data, information from IRENA, and IEA Bioenergy Tasks’ country reports, combined with data provided by the IEA Bioenergy Executive Committee. All individual country reports were reviewed by the national delegates to the IEA Bioenergy Executive Committee, who have approved the content. In the first section of each country report, national renewable energy targets are presented (first table in each country report), and the main pieces of national legislation are discussed. In the second section of each country report the total primary energy supply (TPES) by resources and the contribution of bioenergy are presented. All data is taken from IEA statistics for the year 2014. Where 2014 data was not available, 2013 data was used. It is worth noting that data reported in national statistics can differ from the IEA data presented, as the reporting categories and definitions are different. In the third section of each country report, the research focus related to bioenergy is discussed. Relevant funding programs, major research institutes and projects are described. In the fourth section, recent major bioenergy developments are described. Finally, in the fifth section, links to sources of information are provided.

09 BIOMASS FUELS↗

Technical Report on the Status of Nonlinear Ultrasonic Techniques for Non-Destructive Inspection

This report summarizes technical work conducted by LANL staff and international collaborators in support of the UFD Storage Experimentation effort. The overall focus of this technical work is two-fold: a) on the detection and imaging of a failure mechanism known as stress corrosion cracking (SCC) in stainless steel, and b) on evaluating concrete degradation using nonlinear ultrasonic techniques. This year we report here on three research efforts: 1) experimental effort utilizing TREND and SPACE inspection techniques for crack detection in stainless steel; 2) numerical modeling of 3D time reversal focusing to quantify TREND inspection regions; and 3) application of nonlinear ultrasonic techniques for quantifying concrete degradation. The first and third were collaborative efforts. The first was performed in conjunction with the Tohoku University (Sendai, Japan) and CNRS Parametric Imaging Laboratory (Laboratoire d’Imagerie Parametrique, in Paris, France), with support from the Electricity of France (Électricité de France, [EDF], in Paris, France) project. The third research effort was performed in conjunction with the Federal Institute for Material Research and Testing (Bundesanstalt für Materialforschung und –prüfung, in Berlin, Germany) and The Pennsylvania State University (State College, PA). The conclusion to be made from these results is that nonlinear ultrasound is applicable as a spot inspection technique in both stainless steel and concrete, with the potential to be more broadly applied to other materials and environments. The nonlinear signature measured is related to the degree of damage/degradation. The localized nature of the measurement allows for identification of mechanical defects and localization of degraded regions. Further work is necessary to characterize the degradation (e.g., sensitivity, size of flaws, type of damage, residual strength, etc.). Additionally, for the SCC work to continue to progress, relevant samples must be acquired for study.

36 MATERIALS SCIENCE↗

FY19 Report on the Status of Sodium Exposure Tests of the A709 First Commercial Heat

This report provides an update on the understanding of the effects of sodium exposures on tensile properties of advanced alloy A709 in support of the design and operation of structural components in sodium-cooled fast reactors (SFRs). The focus of the FY19 program was (a) to complete the sodium exposure of sub-sized specimens from A 709 lab heats and 316H (a reference material) and (b) to continue sodium exposure of sub-sized specimens from A 709 commercial heat 58776.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Smart Grid Status and Metrics Report

To convey progress made in achieving the vision of a smart grid, this report uses a set of six characteristics derived from the National Energy Technology Laboratory Modern Grid Strategy. It measures 21 metrics to provide insight into the grid’s capacity to embody these characteristics. This report looks across a spectrum of smart grid concerns to measure the status of smart grid deployment and impacts.

24 POWER TRANSMISSION AND DISTRIBUTION↗