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At least 1,027 records · Page 57
All sourcesNASA NTRSDOE OSTI
NASA NTRSDate not supplied

Overview of NASA's Advanced Air Transport Technology and Revolutionary Vertical Lift Technology Projects, with a Focus on Failure Prevention Research

An overview of NASA Aeronautics is presented with an emphasis on where machinery failure prevention is important to the enterprise. NASA has failure prevention research in areas where new technologies have entered the landscape such as the electrification of propulsion systems. Failure prevention and safety monitoring of machinery is also a routine part of the specialized testing that NASA does.

Reliability, advanced air mobility, subsonic trans↗
NASA NTRSDate not supplied

Planetary Protection, Parts, and Perception: The Ranger Missions as the Origin Story of the Myth of Planetary Protection-Related Mission Failures

There has been a long-standing perspective in the planetary engineering community that the use of planetary protection sterilization techniques such as dry heat microbial reduction (DHMR) have led to significant mission failures in the past. This perception has led to a hesitation to craft mission designs that incorporate sterilization beyond the component-level. Via interviews with long-standing members of the planetary engineering community across the Agency, we have identified the root historical missions that have driven this perspective. The source, or Origin Story, which has been passed down to subsequent generations of engineers, is the failures tied to the early series of the Ranger missions. In this presentation, we examine the details behind the Ranger failures, the majority of which are non-planetary protection sterilization-related, and bring to light the myth of this perception.

planetary protection↗
NASA NTRSDate not supplied

Comparative Analysis for EMU Fleet Latent Loading Characterization in Support of US EVA 80 Failure

During United States Extravehicular Activity 80 (US EVA 80), water was observed in the helmet of an Extravehicular Mobility Unit (EMU) during cabin repressurization. One of the primary mechanisms that can cause water in the helmet of an EMU is integrated performance induced sublimator carryover. The sublimator is a heat exchanger that removes heat and humidity from the ventilation loop. Water vapor is condensed from the gas and removed by slurper holes in the sublimator. Sublimator carryover is caused by the inability of the EMU sublimator to remove all of the condensed water vapor, resulting in liquid water entering the helmet. To determine if sublimator carryover was a likely cause of the US EVA 80 failure, a comparative analysis of numerous historical EVAs was conducted to calculate the total latent load (total water vapor generated by the crewmember) for numerous historical EVAs and ground tests using the Systems Improved Numerical Differencing Analyzer EMU (SINDA EMU) model. The analysis showed that US EVA 80 was associated with a comparatively high latent load when compared to other EVAs that did not present water in the helmet. Further, this analysis showed that other historical EVAs which had visible water in the helmet were also associated with higher latent loads. This analysis provides evidence that the likely cause of the US EVA 80 water in the helmet event was not the failure of an individual component, but rather sublimator carryover caused by excessive production of water vapor by the crewmember. The evidence from this analysis agrees with results from the Test, Teardown, and Evaluation (TT&E) of the EMU which did not show any failure of individual components of the EMU that would lead to water in the helmet.

Noah Andersen↗
NASA NTRS2024

Effects of Oxide Dispersion on Failure Modes in an Additively Manufactured Superalloy

Additive manufacturing opens new paths for introducing oxide particles into superalloys, to potentially provide oxide dispersion strengthening (ODS) at high temperatures. This provides opportunities to study how such dispersions can influence failure modes for a given superalloy, after nearly identical material processing paths. The objective of this study was to compare monotonic failure modes for additively manufactured superalloys with versus without an introduced oxide dispersion. The superalloy for each case was produced by laser powder bed fusion additive manufacturing. Specimens were subsequently given consistent thermal treatment paths and then tested in tensile and creep tests at varied temperatures. Failure modes were then compared. Additively manufactured NiCrAl without ODS had randomly oriented equiaxed grains while this alloy with 0.25 wt% Y 2 O 3 ODS additions had elongated [001] oriented grains in the build direction. Material made without ODS (“No-ODS”) was nearly completely single phase gamma, while ODS additions resulted in gamma, chromium carbide, and Y-Al-Cr oxide phases, with carbide and oxide phases contents estimated at no more than 13 and 1 vol%, respectively. Compared to No-ODS, material made with ODS had higher tensile strengths at room, 760 and 1093 °C. The elongation of ODS material was lower than No-ODS at room temperature, but higher at 760 °C. At 1093 °C ODS material had higher elongation than No-ODS when tested in the build direction, however elongation was lower for ODS material in the transverse direction at 1093 °C. Creep rupture strain, life, and area reduction at 760 and 1093 °C were all much higher for ODS material compared to No-ODS; 760 °C rupture life was nearly 100 times longer for ODS material. The presence of Y in the ODS material significantly improved oxidation resistance.

supperalloys↗
NASA NTRS2024

Cracking Failures in MLCCs and Military Specifications

Failures of MLCCs during applications might indicate problems with the screening and qualification system used. Several cracking related failures of military-grade MLCCs that have been observed over the last few years require analysis of the efficiency and completeness of the procedures used in military specifications. This presentation discusses deficiencies of the currently used procedures to reveal and prevent cracking failures in space projects and possible ways of their improvements.

reliability↗
NASA NTRSDate not supplied

Using AIA Emission Measure Inversion Failures to Track Interesting Flare Physics

EUV channels of the AIA instrument have long been used to characterize the temperature of the plasma, particularly through emission measure inversions. During a solar flare, the instrument can suffer several instrumental artifacts that complicates the analysis. We have performed an analysis of the evolution of two X class flares and find regions where the inversion fails that cannot be easily explained by instrumental artifacts. These failures tend to occur at the top of the flare loop arcade where energy is thought to be released and several non-equilibrium processes may be contributing to the emission of the plasma. In this presentation, I will establish the regions of the emission measure failures and discuss the potential instrumental and physical explanations for these failures.

A R Winebarger↗
DOE OSTI2015

Failure Mechanisms and Color Stability in Light-Emitting Diodes during Operation in High- Temperature Environments in Presence of Contamination

The energy efficiency of light-emitting diode (LED) technology compared to incandescent light bulbs has triggered an increased focus on solid state luminaries for a variety of lighting applications. Solid-state lighting (SSL) utilizes LEDs, for illumination through the process of electroluminescence instead of heating a wire filament as seen with traditional lighting. The fundamental differences in the construction of LED and the incandescent lamp results in different failure modes including lumen degradation, chromaticity shift and drift in the correlated color temperature. The use of LED-based products for safety-critical and harsh environment applications necessitates the characterization of the failure mechanisms and modes. In this paper, failure mechanisms and color stability has been studied for commercially available vertical structured thin film LED (VLED) under harsh environment conditions with and without the presence of contaminants. The VLED used for the study was mounted on a ceramic starboard in order to connect it to the current source. Contamination sources studied include operation in the vicinity of vulcanized rubber and adhesive epoxies in the presence of temperature and humidity. Performance of the VLEDs has been quantified using the measured luminous flux and color shift of the VLEDs subjected to both thermal and humidity stresses under a forward current bias of 350 mA. Results indicate that contamination can result in pre-mature luminous flux degradation and color shift in LEDs.

Lall, Pradeep↗
DOE OSTI2023

PV Inverter Failures Cause AC Breaker Damage - Power Quality

This poster discusses how PV inverter failures cause AC breaker damage and is intended to help system owners identify power quality issues and origins, help inverter and/or circuit breaker manufacturers develop safer failure modes, and develop addendums to standards for failure testing of breakers and inverters.

arc↗
DOE OSTI2022

Predicting failure parameters of semiconductor devices subjected to stress conditions

A method for predicting failure parameters of semiconductor devices can include receiving a set of data that includes (i) characteristics of a sample semiconductor device, and (ii) parameters characterizing a stress condition. The method further includes extracting a plurality of feature values from the set of data and inputting the plurality of feature values into a trained model executing on the one or more processors, wherein the trained model is configured according to an artificial intelligence (AI) algorithm based on a previous plurality of feature values, and wherein the trained model is operable to output a failure prediction based on the plurality of feature values. Further, the method includes generating, via the trained model, a predicted failure parameter of the sample semiconductor device due to the stress condition.

Ahmed, Moinuddin↗
DOE OSTI2017

Failure Evaluation of Savannah River Site High-Level Waste Evaporator 242-25H - Part II - 17353

The Department of Energy's Savannah River Site evaporators are essential to the site actively managing and reducing its liquid high level waste inventory. Since 1951, a series of dedicated evaporators have reduced the liquid waste inventory from 600 ML (160 Mgal) by about a factor of four. The evaporators predominantly have experienced steam tube bundle failures, due to corrosion or fatigue, within about a decade of entering service. To extend service life, recent evaporators have used nickel-based alloys, such as Alloy G-3 (UNS N06030), and have improved operational controls to prevent corrosion. In spite of this, the 242-25H Evaporator recently developed a slow shell leak (0.4 L/min) after sixteen years. An evaporator shell leak is unique in the site's operating history. Finding and characterizing the leak has been challenging because of conflicting information from leak rate data and the locations of externally visible waste. The approaches used to evaluate possible failure modes are described. Failure modes considered include but are not limited to: pressure, temperature, materials, corrosion, fatigue, erosion, and wear. (authors)

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

Mechanical Failure Modes and Longevity of Geo-membranes - 16365

Estimates of the long-term performance of geo-synthetic liner and final cover components have traditionally relied on a small number of standard assumptions originally developed to address the needs of the Resource Conservation and Recovery Act (RCRA) Subtitle D solid waste industry. These past estimates demonstrated that, even under a series of highly conservative factors, the longevity of these components far exceeds the requirements for typical municipal solid waste (MSW) facilities. However, interest in the performance of these components for the disposal of low-level (LLW) and intermediate-level (ILW) radioactive waste landfills has led to additional study of geo-synthetic degradation to address longer assessment periods. These studies allow for the possibility of more rigorous, reliability-based risk assessments of landfill system performance. A particularly strong research need for LLW/ILW facilities is a complete enumeration of the various chemical and mechanical failures modes for geo-membranes serving as final cover and base liner barrier systems. For final covers, failure is defined as allowing an unacceptable flow of water into a containment system. Studies of the various mechanical modes of deformation and rupture for polyethylene sheet allow for a rigorous exploration of the potential causes of geo-membrane barrier system failure. Of particular interest in the performance assessment and engineering of these systems is the ability to use the resulting models to quantify the longevity of these systems with a probabilistic model. An example of this approach is used to illustrate how the consideration of the mechanism for stress cracking in final cover geo-membranes can be adapted for use in simulations of long-term landfill system performance. The results indicate that the effects of cover system design geometry and geo-membrane formulation on performance can be varied significantly by the cover system engineering to meet target performance goals. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Impacts of common cause failure regulatory requirements on protection system architectures - 304

Regulatory-based design considerations for potential common cause failures (CCF) in digital instrumentation and control (I and C) systems have evolved over time and have impacted the development of protection system I and C architectures. The single failure criterion used to be the main design driver for a protection system I and C architecture and resulted in the familiar four-fold and three-fold system architectures. The single failure criterion has now been replaced by the conservative assumptions associated with digital CCF concerns (i.e., assumed digital CCF coincident with an anticipated operational transient or postulated accident) which are classified as 'beyond design basis events' by regulatory authorities. It is unusual for a beyond design basis event to be the controlling factor for a safety system design but that is now the reality for I and C system designers. The preferred regulatory solution is to introduce diversity into I and C system designs to guard against the general concern of digital CCF. However, the lack of clear criteria on how to define sufficient diversity (i.e., how much, what kind, and whether it is linked to identified digital CCF vulnerabilities) had led to more complex I and C architectures. The trend has been towards lengthy and more difficult reviews for the treatment of digital CCF vulnerabilities and I and C system architectures because of the subjective definition of digital CCF vulnerabilities and the lack of clear acceptance criteria for diversity strategy. Improvement in the treatment of digital CCF is needed to reverse the trend of increased I and C system architecture complexity and longer regulatory reviews. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

Nuclear power plant instrumentation and control cyber security common vector access leading to relational common cause failures - 340

Nuclear power plants and facilities have been implementing digital system upgrades into their previously analog systems for well over twenty years. New nuclear facilities' control, security, and emergency preparedness systems are almost exclusively built on digital architectures with a high degree of communication between the various systems that are often integrated together into a central control station to aid in operation or security of the facility. As digital systems become more widespread in nuclear facility control system architectures, cyber security related issues have become a significant concern to operators, regulators, governments, and other groups. Among the many concerns related to digital systems and cyber security is the area of common cause and common mode failures. This paper introduces, defines, and discusses some sources of common cause failure from a cyber security perspective: common vector access. This refers to specific access points that an adversary can exploit through a single attack sequence that have the potential to provide relational failures through common cause on multiple components, subsystems, systems, or plants. This paper will further discuss interconnected processes where these access points may exist, the importance of limiting or controlling these pinch points, and some methods of protecting common vector access points. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

NRC technical basis for evaluation of its position on protection against common cause failure in digital systems used in nuclear power plants - 378

Digital technology has advantages over analog systems, including automated monitoring and alerts for standby safety functions, and predictive algorithms to maintain critical safety systems. Additionally, digital technology generally has higher reliability and can be designed to reduce single point vulnerabilities. For these reasons many nuclear plants have applied digital technology to safety and non-safety related applications, including reactor protection system, feedwater and turbine controls, etc. with a corresponding significant improvement in trip reduction. Nonetheless, digital instrumentation and control (I and C) systems also present potential new vulnerabilities that need to be assessed, including potential failures due to increased complexity of digital systems, the introduction of unique failure modes due to software (including software common cause failure (CCF)), and limited operating history of digital systems in nuclear safety related applications compared to analog systems. The fact that software is intangible means that common methods, such as analysis or testing, used for detecting CCF may not be effective when applied to software. Consequently, digital technology is perceived to pose a potential risk from the introduction of undetected systematic faults that could result in CCF. Despite the I and C system upgrades and modifications performed to date, the U.S. Nuclear Regulatory Commission (NRC) and industry stakeholders have identified the need to modernize the regulatory infrastructure to efficiently address risks associated with the use of digital technology for nuclear safety applications and address regulatory uncertainties. The NRC's current position on CCF is guided by the staff requirements memorandum (SRM) on SECY 93-087. The SRM provides specific acceptance criteria for the evaluation of CCF, which the staff implemented in the Branch Technical Position (BTP) 7-19. However, industry stakeholders have proposed using methods to characterize the likelihood of software CCF and eliminate it from further consideration in a defense-in-depth and diversity analysis. The NRC's current position does not consider these alternatives, and thus corresponding acceptance criteria is not currently available. The work discussed in this paper assesses the underlying technical basis associated with CCF, provides technical support for updating the NRC position and considers proposed methods for addressing potential CCF in digital systems while enhancing efficiency, clarity, and confidence. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2016

Failure Diagnosis for the Holdup Tank System via ISFA

This paper discusses the use of the integrated system failure analysis (ISFA) technique for fault diagnosis for the holdup tank system. ISFA is a simulation-based, qualitative and integrated approach used to study fault propagation in systems containing both hardware and software subsystems. The holdup tank system consists of a tank containing a fluid whose level is controlled by an inlet valve and an outlet valve. We introduce the component and functional models of the system, quantify the main parameters and simulate possible failure-propagation paths based on the fault propagation approach, ISFA. The results show that most component failures in the holdup tank system can be identified clearly and that ISFA is viable as a technique for fault diagnosis. Since ISFA is a qualitative technique that can be used in the very early stages of system design, this case study provides indications that it can be used early to study design aspects that relate to robustness and fault tolerance. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2023

Multifidelity Active Learning for Failure Estimation of TRISO Nuclear Fuel

The Tristructural isotropic (TRISO)-coated particle fuel is a robust nuclear fuel proposed to be used for multiple modern nuclear technologies. Therefore, characterizing its safety is vital for the reliable operation of nuclear technologies. However, the TRISO fuel failure probabilities are small and the computational model is time consuming to evaluate them using traditional Monte Carlo-type approaches. In the paper, we present a multifidelity active learning approach to efficiently estimate small failure probabilities given an expensive computational model. Active learning suggests the next best training set for optimal subsequent predictive performance and multifidelity modeling uses cheaper low-fidelity models to approximate the high-fidelity model output. After presenting the multifidelity active learning approach, we apply it to efficiently predict TRISO failure probability and make comparisons to the reference results.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2024

Interim Development of new Class B Code Case with Variable Design Lifetime and enhanced design rules to guard against cyclic structural failure mode

This report summarizes updates on the ongoing development of the new American Society of Mechanical Engineers Section III, Division 5, Class B rules to address the potential failure modes of Class B components. An initial design-by-analysis approach and supporting design rules are presented. The elastic-perfectly plastic (EPP) analysis approach has been adopted for primary stress limit and ratcheting check to prevent the component failure against the structural failure mode against primary load and strain accumulation due to cyclic loads. The creep-fatigue damage assessment uses explicitly defined elastic follow-up calculated from the stress concentration region of given component. Damage fraction calculation uses a novel coupled approach to capture the influence of the elastic follow-up and provide adequate conservatism for Class B components. The proposed Class B rules does not use the stress classification approach and uses the combined loads to assess component.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Failure time distributions for complex equipment

The exponential distribution is inadequate as a failure time model for most components; however, under certain conditions (in particular, that component failure rates are small and mutually independent, and failed components are immediately replaced or perfectly repaired), it is applicable to complex repairable systems with large numbers of components in series, regardless of component distributions, as shown by Drenick in 1960. This result implies that system behavior may become simpler as more components are added. We review necessary conditions for the result and present some simulation studies to assess how well it holds in systems with finite numbers of components. Lastly, we also note that Drenick's result is analogous to similar results in other systems disciplines, again resulting in simpler behavior as the number of entities in the system increases.

42 ENGINEERING↗