Search NASA⌕ Search

SEARCH · Search NASA

Results for “technical issues”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 127 records · Page 7

The NASA "PERS" Program: Solid Polymer Electrolyte Development for Advanced Lithium-Based Batteries

In fiscal year 2000, The National Aeronautics and Space Administration (NASA) and the Air Force Research Laboratory (AFRL) established a collaborative effort to support the development of polymer-based, lithium-based cell chemistries and battery technologies to address the next generation of aerospace applications and mission needs. The ultimate objective of this development program, which was referred to as the Polymer Energy Rechargeable System (PERS), was to establish a world-class technology capability and U.S. leadership in polymer-based battery technology for aerospace applications. Programmatically, the PERS initiative exploited both interagency collaborations to address common technology and engineering issues and the active participation of academia and private industry. The initial program phases focused on R&D activities to address the critical technical issues and challenges at the cell level. Out of a total of 38 proposals received in response to a NASA Research Announcement (NRA) solicitation, 18 proposals (13 contracts and 5 grants) were selected for initial award to address these technical challenges. Brief summaries of technical approaches, results and accomplishments of the PERS Program development efforts are presented. With Agency support provided through FY 2004, the PERS Program efforts were concluded in 2005, as internal reorganizations and funding cuts resulted in shifting programmatic priorities within NASA. Technically, the PERS Program participants explored, to various degrees over the lifetime of the formal program, a variety of conceptual approaches for developing and demonstrating performance of a viable advanced solid polymer electrolyte possessing the desired attributes, as well as several participants addressing all components of an integrated cell configuration. Programmatically, the NASA PERS Program was very successful, even though the very challenging technical goals for achieving a viable solid polymer electrolyte material or the overall envisioned long-term, program objectives were not met due to funding reductions. The NASA PERS Program provided research opportunities and generated and disseminated a wealth of new scientific knowledge and technical competencies within the polymer electrolyte area.

Baldwin, Richard S.↗

Progress and Challenges of Additive Manufacturing of Tungsten and Alloys as Plasma-Facing Materials

Tungsten (W) and W alloys are considered as primary candidates for plasma-facing components (PFCs) that must perform in severe environments in terms of temperature, neutron fluxes, plasma effects, and irradiation bombardment. These materials are notoriously difficult to produce using additive manufacturing (AM) methods due to issues inherent to these techniques. The progress on applying AM techniques to W-based PFC applications is reviewed and the technical issues in selected manufacturing methods are discussed in this review. Specifically, we focus on the recent development and applications of laser powder bed fusion (LPBF), electron beam melting (EBM), and direct energy deposition (DED) in W materials due to their abilities to preserve the properties of W as potential PFCs. Additionally, the existing literature on irradiation effects on W and W alloys is surveyed, with possible solutions to those issues therein addressed. Finally, the gaps in possible future research on additively manufactured W are identified and outlined.

36 MATERIALS SCIENCE↗

Assessment of Lithium-based Battery Electrolytes Developed under the NASA PERS Program

Recently, NASA formally completed the Polymer Energy Rechargeable System (PERS) Program, which was established in 2000 in collaboration with the Air Force Research Laboratory (AFRL) to support the development of polymer-based, lithium-based cell chemistries and battery technologies to address the next generation of aerospace applications and mission needs. The goal of this program was to ultimately develop an advanced, space-qualified battery technology, which embodied a solid polymer electrolyte (SPE) and complementary components, with improved performance characteristics that would address future aerospace battery requirements. Programmatically, the PERS initiative exploited both interagency collaborations to address common technology and engineering issues and the active participation of academia and private industry. The initial program phases focused on R&D activities to address the critical technical issues and challenges at the cell level. A variety of cell and polymeric electrolyte concepts were pursued as part of the development efforts undertaken at numerous governmental, industrial and academic laboratories. Numerous candidate electrolyte materials were developed, synthesized and optimized for evaluation. Utilizing the component screening facility and the "standardized" test procedures developed at the NASA Glenn Research Center, electrochemical screening and performance evaluations of promising candidate materials were completed. This overview summarizes test results for a variety of candidate electrolyte materials that were developed under the PERS Program. Electrolyte properties are contrasted and compared to the original project goals, and the strengths and weaknesses of the electrolyte chemistries are discussed. Limited cycling data for full-cells using lithium metal and vanadium oxide electrodes are also presented. Based on measured electrolyte properties, the projected performance characteristics and temperature limitations of batteries utilizing the advanced electrolytes and components have been estimated. Limitations for the achievement of practical performance levels are also discussed, as well as needs for future research and development.

Bennett, William R.↗

Polymer Energy Rechargeable System (PERS) Development Program

The National Aeronautics and Space Administration (NASA) and the Air Force Research Laboratory (AFRL) have recently established a collaborative effort to support the development of polymer-based, lithium-based cell chemistries and battery technologies to address the next generation of aerospace applications and mission needs. The overall objective of this development program, which is referred to as PERS, Polymer Energy Rechargeable System, is to establish a world-class technology capability and U.S. leadership in polymer-based battery technology for aerospace applications. Programmatically, the PERS initiative will exploit both interagency collaborations to address common technology and engineering issues and the active participation of academia and private industry. The initial program phases will focus on R&D activities to address the critical technical issues and challenges at the cell level.

Baldwin, Richard S.↗

DOE EM Sponsored Research on Long-Term Dry Storage of Aluminum Clad SNF

This PowerPoint presentation describes and discusses DOE EM and INL lead studies on addressing potential technical issues associated with long-term dry storage of aluminum clad spent nuclear fuel. This same presentation was made to the US Nuclear Waste Technical Review Board in Nov 2019.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Managing Risks via Small/Pilot Scale Testing for INL's Integrated Waste Treatment Unit (IWTU) - 19268

In 2005, the THOR steam reforming fluidized-bed reactor (FBR) technology was selected by the U.S. Department of Energy (DOE) as the technology of choice for treatment of sodium- bearing waste (SBW) at the INL. The basis of the process was to use fluidized bed technology to convert an acidic radioactive nitrate-rich liquid waste into a solid carbonate product suitable for long-term disposal and storage. During initial commissioning, as well as subsequent start-ups, the plant faced many operational challenges, such as stagnant/de-fluidized bed, and wall-scale formation. Such operational issues prompted the original contractor to seek expertise in pilot-scale testing, thereby reaching out to Hazen Research Inc. (HRI, Golden, Co). Several tests were conducted, but the results did not seem to address the underlying issues observed in the full-scale plant, as evidenced by continued operational issues. A systematic approach was then taken by the Fluor-Idaho team (new contractor as of June 2016) with respect to solving these technical issues. First, two different bench-scale, 2-inch fluidized bed reactors (stainless-steal and quartz), were utilized to test several theories to better understand the underlying chemical reactions that may be taking place under expected normal operating conditions. Then, the team designed and built an 18-inch FBR unit, mimicking the full-scale main vessel at IWTU - Denitration Mineralization Reformer (DMR). This was used to test various aspects of operational challenges observed at IWTU, namely particle size control, wall-scale growth-rate control, long-term operational stability, process optimization, and process off- gas filtration challenges. An example of information obtained from bench-scale testing, which was then tested during pilot-scale testing, was the phenomena that an addition of 5 vol % of CO{sub 2} gas into the fluidizing gas system nearly eliminated the formation of agglomerates that had typically led to bed de-fluidization. This change proved to be correct in both the pilot and full-scale testing and will be implemented as part of a long-term operational strategy of IWTU. Several other findings that have provided answers with respect to IWTU operational issues will be discussed in this report. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NEP systems engineering efforts in FY-92: Plans and status

A system engineering effort has been initiated by NASA in FY-92 to define, address, and resolve issues associated with the use of Nuclear Electric Propulsion (NEP) for megawatt (MW) space propulsion applications associated with the Space Exploration Initiative (SEI). It is intended that key technical issues will be addressed by activities conducted in the early years of a project in NEP, with the objective of resolving such issues. Also, in response to more recent programmatic direction, a concept definition activity for 100 kilowatt NEP is being initiated. This paper will present key issues associated with megawatt NEP, and the plans and status for their resolution, and present the scope and rationale for the 100 kilowatt concept definition activity.

Doherty, Michael P.↗

Technical Challenges for Next Generation Composite Duct Technology

The Access to Space Study identified the requirement for lightweight structures to achieve orbit with a single stage vehicle. The use of composite components partially fulfills that requirement. The purpose of this presentation is to review the technical challenges in the use of composite materials and processes for lines and ducts on next generation launch vehicles. This presentation will identify current requirements for space and missile system components; review the state of the art for existing system components; identify show stoppers to advancing the state of the art; identify technical issues that might limit the application of advanced materials; identify key materials that might provide a high payoff; and identify opportunities for joint partnerships to overcome these multiple technical challenges.

Ledbetter, Frank E., III↗

Preferred Concepts for Disposal of the UK Inventory of Depleted, Natural and Low Enriched Uranium - 16382

Depleted, natural and low enriched uranium (DNLEU) forms a significant quantity of the UK inventory of higher activity radioactive materials. The great majority comprises uranic materials produced from uranium enrichment operations and from reprocessing of spent nuclear fuels. The most recent estimate of the total quantity (stocks plus arisings) of UK-owned DNLEU from civil nuclear operations is 170,000 tU. Current UK Government strategy is for DNLEU to be stored indefinitely in existing or new facilities, as required. However, Government strategy for long-term management of uranic materials is under review and a change could potentially cause this material to be reclassified as a waste. An Integrated Project Team (IPT) was formed in 2012 with the objective of identifying and addressing the issues associated with the potential need to dispose of DNLEU, in order to inform wider decision-making on the long-term management of UK DNLEU. Key technical issues considered by the IPT relate to the following: 1. The need for an improved understanding of the UK DNLEU inventory. 2. The identification of preferred chemical and physical form(s), and preferred packaging and disposal concepts for DNLEU - the main subject of this paper. 3. The approach to safety assessment of DNLEU disposal. This paper summarises the disposal concepts under consideration by the IPT, and the rationale for identification of preferred concepts for disposal of DNLEU inventory components. The conclusions will be of interest to other programmes and countries with a requirement to manage large quantities of similar materials. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Application of Refractory High-Entropy Alloys for Higher-Reliability and Higher-Efficiency Brayton Cycles and Advanced Nuclear Reactors

An exceptional set of newly-discovered advanced superalloys known as refractory high-entropy alloys (RHEAs) can provide near-term solutions for wear, erosion, corrosion, high-temperature strength, creep, and radiation issues associated with supercritical carbon dioxide (sCO2) Brayton Cycles and advanced nuclear reactors. In particular, these superalloys can significantly extend their durability, reliability, and thermal efficiency, thereby making them more cost-competitive, safer, and reliable. For this project, it was endeavored to manufacture and test certain RHEAs, to solve technical issues impacting the Brayton Cycle and advanced nuclear reactors. This was achieved by leveraging Sandia’s patents, technical advances, and previous experience working with RHEAs. Herein, three RHEA manufacturing methods were applied: laser engineered net shaping, spark plasma sintering, and spray coating. Two promising RHEAs were selected, HfNbTaZr and MoNbTaVW. To demonstrate their performance, erosion, structural, radiation, and hightemperature experiments were conducted on the RHEAs, stainless steel (SS) 316 L, SS 1020, and Inconel 718 test coupons, as well as bench-top components. The experimental data is presented, analyzed, and confirms the superior performance of the HfNbTaZr and MoNbTaVW RHEAs vs. SS 316 L, SS 1020, and Inconel 718. In addition, to gain more insights for larger-scale RHEA applications, the erosion and structural capabilities for the two RHEAs were simulated and compared with the experimental data. The experimental data confirm the superior performance of the HfNbTaZr and MoNbTaVW RHEAs vs. SS and Inconel. Most importantly, the erosion and the coating material experimental data show that erosion in sCO2 Brayton Cycles can be eliminated completely if RHEAs are used. The experimental suite and validations confirm that HfNbTaZr is suitable for harsh environments that do not include nuclear radiation, while MoNbTaVW is suitable for harsh environments that include radiation.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Materials sub-panel

The following subject areas are covered: general issues (unique operating/storage environments, adapt existing materials/develop rocket materials, long lead time for new materials, high cost, integration of materials development and manufacturing technology, and availability of materials data); technical issues (materials characterization for operating and storage environments, advanced materials development, availability and dissemination of materials properties, advanced materials tests facilities, fire hazards, and propellants); major objectives (materials characterization, advanced materials development, and materials data base development/maintenance); and candidate programs (materials characterization, advanced materials development, and aerospace materials data base).

Bhat, Bil↗

IGS 1996 Analysis Center Workshop

Components of the IGS[International GPS (Global Positioning System) Service for geodynamics], have operated a GPS tracking system for several years. The network now contains more than 100 stations and has produced a combined GPS ephemeris that has become the standard for geodesists and geophysicists worldwide. IGS data and products are freely available to all thanks to the cooperation and participation of all the IGS members. The IGS has initiated development of several new products, and technical issues permitting greater accuracy of IGS products have been identified. The IGS convened a workshop on March 1996 in Silver Spring, Maryland, USA, to coordinate these developments and to examine technical problems and solutions. The following topics were addressed: orbit/clock combination; Earth orientation; antenna calibration; SINEX and densification of the International Terrestrial Reference Frame (ITRF) using the GPS; receiver standards and performance; and atmospheric topics.

Neilan, R. E.↗

Planetary Protection and Mars Exploration

Planetary spacecraft to explore Mars are subject to international and NASA policy regarding biological cleanliness. This policy is referred to as planetary protection and it establishes guidelines to prevent biological cross-contamination of planets during solar system exploration missions. Mars mission designs and exploration strategies are incomplete without consideration of planetary protection. In this paper, the foundation for planetary protection policy will be reviewed and key issues identified. Existing guidelines governing both forward and back contamination will be summarized. Various Mars exploration scenarios will be examined and the impact of planetary protection requirements will be assessed. Technical issues that need resolution will also be identified. Finally, there will be a discussion of anticipated public attitudes concerning the risk of back contamination from Mars sample return missions.

DeVincenzi, D. L.↗

Radiological Soil Sorting Considerations and Applications - 19363

A number of methods are available for soil sorting, specifically sorting of radiological materials. These methods have been applied from the Feasibility Study stage of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) in pilot study operations to full scale operations in the post Record of Decision stages at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. This application of sorting at multiple sites and under many different conditions has provided the United States Army Corps of Engineers (USACE) with many challenges and lessons learned. Mechanical soil sorting has had varying degrees of success and many factors have been evaluated. Some factors include the type of material that is best suited for sorting, contaminant distribution, and pre-screening of materials. Community acceptance is another non-technical issue that can be key in applying sorting to a FUSRAP cleanup. This paper will discuss multiple types of radiological soil sorting to include reversing belt conveyor, segmented gate, and manual as well as technical considerations and the factors impacting each type. Additionally, how and when soil sorting is applied to FUSRAP operations is discussed. The FUSRAP is conducted in accordance with CERCLA and the impacts to how sorting is applied in terms of considering it treatment under CERCLA will also be discussed. This paper and presentation will be useful for any project considering using radiological soil sorting. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Importance of Getting it Right - Lessons from the Failure and Subsequent Approval of the LLWR Environmental Safety Case - 16691

The Low Level Waste Repository (LLWR) in the UK submitted an Environmental Safety Case in 2002 which was rejected by the Environment Agency 3 years later. Almost a decade after the rejection, the LLWR submitted a completely different document which was approved in November 2015. This paper looks at the lessons learned from the failed submission and documents the strategy employed by the Site's new contractor to overcome both the challenging technical issues that led to the initial rejection and overcome the resistance to long term disposal by the local community. It will describe the journey it has taken to move from a flawed safety case, to a technically sound safety case, to one that is approved by the regulator, and accepted by the community. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The DOE Criticality safety support group - A retrospective perspective - 14580

The Department of Energy (DOE) Nuclear Criticality Safety Support Group (CSSG) came into being as a response to the DNFSB recommendation 1997-2 'Criticality Safety' which dealt with the continuation of criticality safety at defense nuclear facilities in the Department of Energy Enterprise. The DNFSB was concerned over the lack of capability management of practical experience pertinent to avoiding a criticality accident in non-reactor environments. One of the specific recommendations of 1997-2 was to 'Identify a core group of criticality experts experienced in the theoretical and experimental aspects of neutron chain reactions to advise on the above steps and assist in resolving future technical issues'. The CSSG, a group of 10 recognized experts in criticality safety, was chartered in late 1997 to address the recommendation. Members of the CSSG are drawn from DOE employees and contractor staff to provide advice and technical support to help meet the criticality safety needs of DOE missions, including stockpile stewardship, materials stabilization, transportation, storage, facilities life cycle (design through decommissioning), and waste disposal. The CSSG is an integral part of the DOE Nuclear Criticality Safety Program (NCSP) developed to maintain and enhance the operational and technical criticality safety expertise and capability within the Department of Energy Enterprise. This paper outlines the history, purpose and continuing contribution of the CSSG as well as providing an understanding of the interfaces between the DOE CSSG, the DOE Criticality Safety Coordinating Team (CSCT), the ANS Nuclear Criticality Safety Division and the EFCOG Criticality Safety Subgroup. (authors)

42 ENGINEERING↗

Introduction to System Health Engineering and Management in Aerospace

This paper provides a technical overview of Integrated System Health Engineering and Management (ISHEM). We define ISHEM as "the paper provides a techniques, and technologies used to design, analyze, build, verify, and operate a system to prevent faults and/or minimize their effects." This includes design and manufacturing techniques as well operational and managerial methods. ISHEM is not a "purely technical issue" as it also involves and must account for organizational, communicative, and cognitive f&ms of humans as social beings and as individuals. Thus the paper will discuss in more detail why all of these elements, h m the technical to the cognitive and social, are necessary to build dependable human-machine systems. The paper outlines a functional homework and architecture for ISHEM operations, describes the processes needed to implement ISHEM in the system life-cycle, and provides a theoretical framework to understand the relationship between the different aspects of the discipline. It then derives from these and the social and cognitive bases a set of design and operational principles for ISHEM.

Johnson, Stephen B.↗

Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

The U. S. NRC is currently proposing rulemaking designated as “10 CFR 50.46c” to revise the loss-of-coolant-accident (LOCA)/emergency core cooling system (ECCS) acceptance criteria to include the effects of higher burnup on cladding performance as well as to address other technical issues. The NRC is also currently resolving the public comments with the final rule expected to be issued in April 2016. The impact of the final 50.46c rule on the industry may involve updating of fuel vendor LOCA evaluation models, NRC review and approval, and licensee submittal of new LOCA evaluations or re-analyses and associated technical specification revisions for NRC review and approval. The rule implementation process, both industry and NRC activities, is expected to take 4-6 years following the rule effective date. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The proposed rule would apply to a light water reactor and to all cladding types.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗