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At least 1,747 records · Page 97
All sourcesNASA NTRSDOE OSTI
DOE OSTI2021

Challenges of Interpreting and Applying New IPC-J-STD-001 Cleanliness Standards in High-Reliability Applications

The electronics industry has rapidly and widely embraced the replacement of ROSE testing with an SIR-focused approach to testing for certification of a qualified manufacturing plan. These new cleanliness documentation standards, housed in IPC J-STD-001 Rev. H, have just begun to impact electronics manufacturers as design and production teams work through how to meet them. This research focuses on the particular challenges of applying these new standards in high-reliability product applications, through the lens of interpreting SIR test results and what they mean for process capability, repeatability and diagnosing a need for process changes. The experiments examined a variety of factors that influence SIR results and suggest areas where SIR test plans can be greatly improved.

Capen, William↗
DOE OSTI2020

Standardized Architecture for a Mega-Biobank Phenomic Library: The Million Veteran Program (MVP)

Electronic health records (EHRs) provide a wealth of data for phenotype development in population health studies, and researchers invest considerable time to curate data elements and validate disease definitions. The ability to reproduce well-defined phenotypes increases data quality, comparability of results and expedites research. In this paper, we present a standardized approach to organize and capture phenotype definitions, resulting in the creation of an open, online repository of phenotypes. This resource captures phenotype development, provenance and process from the Million Veteran Program, a national mega-biobank embedded in the Veterans Health Administration (VHA). To ensure that the repository is searchable, extendable, and sustainable, it is necessary to develop both a proper digital catalog architecture and underlying metadata infrastructure to enable effective management of the data fields required to define each phenotype. Our methods provide a resource for VHA investigators and a roadmap for researchers interested in standardizing their phenotype definitions to increase portability.

Knight, Kathryn↗
DOE OSTI2021

ASME Code Rules and ASTM Standards Integration for Ceramic Composite Core Materials and Components 1

Fiber-reinforced ceramic matrix composites have many desirable properties for high-temperature nuclear applications, including excellent thermal and mechanical properties and reasonable to outstanding radiation resistance. Over the last 20 years, the use of ceramic composite materials has already expanded in many commercial nonnuclear industries as fabrication and application technologies mature. The new ASME design and construction rules under Section III, Subsection HH, Subpart B lay out the requirements and criteria for materials, design, machining and installation, inspection, examination, testing, and the marking procedure for ceramic composite core components, which is similar to the established graphite code under Section III, Subsection HH, Subpart A. Moreover, the general requirements listed in Section III, Subsection HA, Subpart B are also expanded to include ceramic composite materials. The code rules rely heavily on the development and publication of standards for composite specification, classification, and testing of mechanical, thermal, and other properties. These test methods are developed in the American Society for Testing and Materials Committee C28 on Advanced Ceramics with a current focus on ceramic composite tubes. Details of the composites code, design methodology, and similarities to the graphite code, as well as guidance for the development of specifications for ceramic composites for nuclear application and recent standard developments, are discussed. The next step is to "close the gap" to support licensing aspects by validating the code with benchmarking data.

Geringer, Josina↗
DOE OSTI2017

Standards and Guidelines for the Design of Trunnions of RAM Transport Packages - 17365

Trunnion systems of packages for the transport of radioactive materials have to guarantee the safe handling of package during crane operations (lifting, tilting) and to secure package tie down to the transport vehicle, if the trunnions are used as attachment points during transport. The design of trunnions is based on IAEA Regulations SSR-6, the supporting Advisory Material SSG-26 and further appropriate technical standards and/or guidelines. For package approval procedures in Germany the guideline BAM-GGR 012 has to be applied. If a package is handled inside a german nuclear power plant, the standard KTA 3905 has to be fulfilled additionally. In this paper the requirements of KTA 3905 [4] concerning the trunnion systems as load attaching points (LAP) are discussed in connection with the recommendations in the guideline BAM-GGR 012 [3]. This guideline is prepared at BAM Federal Institute for Materials Research and Testing for analysis and assessment of bolted lid and trunnion systems of Type B(U) transport packages. The quality assurance questions concerning trunnion systems are discussed as well. (authors)

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

Innovative Solutions for Loading Smaller Standardized Dry Storage Canister Systems for Used Nuclear Fuel - 16232

An integrated team lead by EnergySolutions has developed and evaluated design concepts and loading processes for standardized transportation, aging and disposal (STAD) canister systems for the dry storage of United States (US) commercial used nuclear fuel (UNF). These STADs would be smaller than the Dual Purpose Canisters (DPCs) currently in use for storage and transportation of UNF at the nuclear power plant (NPP) sites in the US, so it was necessary to study the operational requirements and impacts related to their implementation at the NPPs and develop innovative approaches to mitigate these impacts. This work was funded by the US Department of Energy (DOE) to support the DOE in evaluating the option of using standardized canister systems for storage, transport, and disposal of US commercial UNF as part of an integrated waste management system. The NPP utilities are currently placing UNF into increasingly large DPCs because this reduces loading times and associated worker dose uptake. However, whether large DPCs may be able to be directly disposed is not known at this time, and will depend in part on future geologic disposal concepts and the DPC heat content. The use of STAD canisters rather than DPCs at the NPP sites and/or at an interim storage facility could avoid a potential need to repackage the UNF for disposal but, to make STAD canisters attractive for use, ways need to be found to fill and seal them efficiently from an operational perspective. This paper describes the generic design for a small STAD canister system, the loading processes and process improvements that were identified for the small, medium and large STAD canister sizes, the methodology for, and results from, the assessment of the performance of the loading processes, and the practicality of the results versus NPP operating experience. The work that this paper reports thus reflects research and development efforts to explore technical concepts that could support future decision-making by DOE. (authors)

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

UPF Data Book: A Resource for Standard Data, Dimensions, Equations, and Practices used at UPF for Nuclear Criticality Safety Analyses

A new Uranium Processing Facility (UPF) is being designed at Y-12 in Oak Ridge to replace the existing facilities. As part of this design, new and existing processes need to be evaluated using Criticality Safety Process Studies (CSPS) to ensure they remain subcritical for both normal and credible abnormal conditions. This requires a great many sets of calculations using both MCNP and SCALE to model the various configurations, concentrations, and processes being designed. At UPF these calculations are contained within Design Analysis and Calculation (DAC) documents. Without a standard guide different nuclear criticality safety (NCS) engineers were modeling the same system using parameters familiar to them from past experience. Often this resulted in significantly different assumptions on things such as: materials, uranium enrichment, reflection conditions, and maximum uranium concentrations for calculations in DACs supporting essentially the same process but in a different CSPS. It became apparent that, for DACs to be useful for more than the CSPS they were written to support, a common set of guidelines, for use by all NCS engineers, was needed. A Data Book DAC is now used at UPF to help standardize the common UPF system parameters used for all calculations. This makes it possible to use existing calculations from one CSPS in another CSPS having similar processes. It also simplifies the requirements imposed by NCS on things like pipe diameters, tank size and spacing, and component placement on the design and process disciplines. Finally, for a given parameter, once it is determined the parameter is valid for a UPF process it becomes valid for all similar processes without the need for further calculational analyses. (authors)

42 ENGINEERING↗
DOE OSTI2024

Fabrication and Testing of DOE Standard Canister Closure Leak Test Assembly

DOE manages over 300 types of spent nuclear fuel (SNF), many of which are located at the Idaho National Laboratory (INL) site. Managing this large variety of SNF for storage, transportation, and disposal poses a challenge to DOE. The Idaho Cleanup Project and INL are collaborating on the DOE SNF Road-Ready Demonstration (“Road-Ready Demonstration”), which will develop and demonstrate the designs, technology, processes, and regulatory framework for packaging DOE-managed SNF for “road-ready dry storage.” Road-ready dry storage is an SNF management concept in which SNF is packaged into dry, sealed canisters that are then placed in onsite storage in anticipation of later transport and disposition. The forward-looking goal of the Road-Ready Demonstration is to establish the foundation for a large-scale road-ready dry storage program at the INL site. In support of establishing a large-scale road-ready dry storage program at the INL site, the Road-Ready Demonstration will first package Fort St. Vrain SNF currently in dry storage at INL into several DOE Standard Canisters (DOESCs). These DOESCs will in turn be loaded into another containment similar to commercial multi-purpose canisters. This multi-purpose canister will then be compatible with a transportation or storage system, such as a storage cask for interim storage or transportation package for offsite transport. These DOESCs will remain sealed over the course of their storage, transportation, and applicable disposal functions. The closure process for the DOESC will include fuel and basket loading, welding, inspection, leak testing, and, if needed, repair. As a follow-up to previous discussions on the design of the DOE Closure Leak Test Assembly (LTA), this report describes recent fabrication and testing efforts performed at INL. DOESCs are sealed by two sequential gas tungsten arc welds, both of which are performed by remotely operated and semiautomatic welding systems. The first weld is a circumferential pipe weld that completes the assembly of the canister body and lid assembly. The second and final closure weld attaches the vent plug to the vent socket via a butt joint. After the second weld is performed, the welds are helium leak tested using an evacuated envelope technique. The LTA was designed for both remote and manual operation. This report describes the fabrication and performance testing associated with the evacuated envelope technique. INL staff designed, fabricated, and tested the LTA at INL facilities. This testing included establishing technique and system sensitivities in accordance with ASME and American National Standards Institute N14.5 requirements. Forthcoming work will cover such areas as design optimization, process and personnel qualification, and implementation in Road-Ready Demonstration operations.

42 ENGINEERING↗
DOE OSTI2023

Fabrication and Testing of DOE Standard Canister Closure Leak Test Assembly – 24139

DOE manages over 300 types of spent nuclear fuel (SNF), many of which are located at the Idaho National Laboratory (INL) site. Managing this large variety of SNF for storage, transportation, and disposal poses a challenge to DOE. The Idaho Cleanup Project and INL are collaborating on the DOE SNF Road-Ready Demonstration (“Road-Ready Demonstration”), which will develop and demonstrate the designs, technology, processes, and regulatory framework for packaging DOE-managed SNF for “road-ready dry storage.” Road-ready dry storage is an SNF management concept in which SNF is packaged into dry, sealed canisters that are then placed in onsite storage in anticipation of later transport and disposition. The forward-looking goal of the Road-Ready Demonstration is to establish the foundation for a large-scale road-ready dry storage program at the INL site. In support of establishing a large-scale road-ready dry storage program at the INL site, the Road-Ready Demonstration will first package Fort St. Vrain SNF currently in dry storage at INL into several DOE Standard Canisters (DOESCs). These DOESCs will in turn be loaded into another containment similar to commercial multi-purpose canisters. This multi-purpose canister will then be compatible with a transportation or storage system, such as a storage cask for interim storage or transportation package for offsite transport. These DOESCs will remain sealed over the course of their storage, transportation, and applicable disposal functions. The closure process for the DOESC will include fuel and basket loading, welding, inspection, leak testing, and, if needed, repair. As a follow-up to previous discussions on the design of the DOE Closure Leak Test Assembly (LTA), this report describes recent fabrication and testing efforts performed at INL. DOESCs are sealed by two sequential gas tungsten arc welds, both of which are performed by remotely operated and semiautomatic welding systems. The first weld is a circumferential pipe weld that completes the assembly of the canister body and lid assembly. The second and final closure weld attaches the vent plug to the vent socket via a butt joint. After the second weld is performed, the welds are helium leak tested using an evacuated envelope technique. The LTA was designed for both remote and manual operation. This report describes the fabrication and performance testing associated with the evacuated envelope technique. INL staff designed, fabricated, and tested the LTA at INL facilities. This testing included establishing technique and system sensitivities in accordance with ASME and American National Standards Institute N14.5 requirements. Forthcoming work will cover such areas as design optimization, process and personnel qualification, and implementation in Road-Ready Demonstration operations.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2024

NOvA Constraints on CP-Violating Non-Standard Interactions

This poster shows the results of work of search for charge-parity (CP) symmetry violating non-standard interactions (NSI) of neutrinos with matter using the NOvA Experiment, and examines their effects on the determination of the standard oscillation parameters.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2025

SaltStone Wastewater Cement Study Using Isothermal Calorimetry, Standard Concrete Characterization Techniques, and CemGEMS - 25169

Cementitious reagents are used to solidify/stabilize aqueous radioactive, hazardous, and mixed salt solutions, and sludges to meet low-level radioactive waste (LLW) and Resource Conservation and Recovery Act (RCRA) requirements for disposal at Department of Energy (DOE). It is flexible enough to solidify radioactive wastewater saturated in complex species that include but are not limited to radioactive isotopes from the bombardment of neutrons in reactor operation, corrosion products from metallic components, and a variety of soluble organic compounds. [1,2]. Waste form testing typically includes processing or fresh properties, cured properties, compressive strength and hydraulic properties, porosity, density, saturated and unsaturated moisture transport, and leachability of contaminants in the waste form pore solution. Properties are collected over a relatively limited time, typically 28 to 365 days [3]. In addition, changes in the waste form as the result of time and changing conditions are important for concrete engineers to predict overall performance of the forms and potential release of contaminants in the disposal process via unintended filtration into the environment [4]. These predictions are determined/calculated characterizing young waste forms (relative to the standard age of concrete) and are based on transport through soluble ions in pore solutions. Characterization methods include X-ray, SEM, and isothermal calorimetry among other methods used to define the composition, amorphous vs. crystalline nature of the components, and the energetic formation mechanisms for multi-phase mineral systems. [5–7] Isothermal calorimetry is a well standardized technique for cements and concretes and can be used to predict the timing and nature of the hydration reactions.[8] The technique can measure long term energetic

Bustamante, Michael E. [Savannah River National La↗
DOE OSTI2025

Unique & challenging aspects of plutonium metal standards exchange program for actinide measurements

The Los Alamos National Laboratory exchange program is the only program of its kind for the distribution of plutonium (Pu) standards materials with a range of impurity contents to multiple laboratories for destructive measurements of elemental concentration. This paper discusses statistical methods used to address challenges in Pu metal exchange data by way of two case studies. Challenges include how to evaluate a data set when a large fraction of the values are minimum detection limits (MDLs), and how to determine potential outliers with limited in-formation on the true spread of the data.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
DOE OSTI2015

Climate-Specific Passive Building Standards

In 2012, the U.S. Department of Energy (DOE) recognized the value of performance-based passive building standards when it joined with Passive House Institute US (PHIUS) to promote DOE’s Challenge Home program in tandem with the PHIUS+ Certification program. Since then, the number of passive building projects that have been certified under the partnership has grown exponentially because of some synergy. Passive building represents a well-developed approach to arrive at the envelope basis for zero energy and energy-positive projects by employing performance-based criteria and maximizing cost-effective savings from conservation before implementing renewable energy technologies. The Challenge Home program evolved into the Zero Energy Ready Home (ZERH) program in a move toward 1) attaining zero energy and 2) including active renewable energy generation such as photovoltaics (PV)—toward the zero energy goal.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2020

Clause-by-Clause Summary of Requirements in IEEE Standard 1547-2018

The revised IEEE 1547 standard (IEEE Std 1547-2018) contains eleven chapters (clauses) and eight annexes that comprise 136 pages. Each clause specifies information or requirements that apply to certain aspects important to the interconnection of distributed energy resources to the electric power system. Implementation of the requirements needs a careful study of the underlying technical concept and also needs the appropriate information that may be required to calculate various settings and configurations. This document aims to provide an introductory text to assist users of IEEE Std 1547-2018 in identifying the following questions: what is the primary audience of the clause/subclause? What knowledge is required to understand the technical subject matter? What information is required to apply/implement the requirements specified? What level of fluency with the subject matter is required to apply/implement the requirements?

24 POWER TRANSMISSION AND DISTRIBUTION↗
DOE OSTI2021

American Nuclear Society ANS-8 Standards Forum [Slides]

The agenda for this forum includes an agenda discussion, membership discussion, a review of recent SC-8 & NCSCC ballots, ISO TC85/SC5/WG8 standards activity report (D. Bowen), NCSCC activity report (L. Wetzel), reports from working group chairs, and old/new business.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2023

American Nuclear Society ANS-8 Standards Forum

This presentation was created to highlight several pertinent topics and reports to introduce into the forum. This presentation covers membership along with the recent SC-8 & NCSCC ballots. Topics discussed include the ISO TC85/SC5/WG8 standards activity with a report from D. Bowen. Additionally, a NCSCC activity report by L. Wetzel was received. Along with reports from working group chairs. Finally, any Old/New Business was introduced.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗
NASA NTRS1996

The Proposed NASA Pyroshock Test Criteria Standard - Part I

The National Aeronautics and Space Administration has traditionally left the task of specifying design and test criteria to each of the several NASA Centers. Faced with the wide variety fo resulting criteria used for resolving similar or identical problems, the NASA Office of Chief Engineer initiated a program to develop consistent NASA-wide standards if the various NASA Centers could agree to a set of common requirements.

pyrotechnic shock shock testing pyrotechnic testin↗