Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “PROPOSALS”

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 307 records · Page 17

Proposal and Evaluation of Subordinate Standard Solar Irradiance Spectra: Preprint

This paper introduces a concept for global tilted irradiance (GTI) subordinate standard spectra to supplement the current standard spectra used in solar photovoltaic applications as defined in ASTM G173 and IEC60904. The proposed subordinate standard spectra correspond to atmospheric conditions and tilt angles that depart significantly from the main standard spectrum, and they can be used to more accurately represent various local conditions. For the definition of subordinate standard spectra cases with an elevation 1.5 km above sea level, the question arises whether the air mass should be calculated including a pressure correction or not. This study focuses on the impact of air mass used in standard spectra, and it uses data from 29 locations to examine which air mass is most appropriate for GTI and direct normal irradiance (DNI) spectra. Overall, it is found that the pressure-corrected air mass of 1.5 is most appropriate for DNI spectra. For GTI, a non-pressure-corrected air mass of 1.5 was found to be more appropriate.

14 SOLAR ENERGY↗

XDV: A proposal for an X-ray Doppler Velocimetry diagnostic

Presentation describes proposal to arrange several bent crystals, each tuned to a different center wavelength within the motional Doppler-broadened profile of a suitable x-ray emission line, to produce a multispectral image that maps wavelength shift to line-of-sight velocity.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Proposed Enhanced Imaging Station in the 6-GeV Booster-to-Storage Ring Transport Line for APS Upgrade

The high charge per micropulse of up to 17 nC in the booster to storage ring transport line (BTS) for APS Upgrade will necessitate changes in the imaging station used to evaluate beam emittance in this key region. The original Chromox screen has recently been replaced by a YAG:Ce single crystal for immediate screen spatial resolution improvement down to <10 µm. However, the optical system also needs an upgrade with lenses and a digital camera to take full advantage of this enhancement. In addition, at the high areal charge densities expected, the YAG:Ce scintillator mechanism will saturate, or quench, leading to images larger than the actual beam size. To circumvent this effect, optical transition radiation (OTR) screens will be implemented. A proposed longer-range goal of a non-intercepting beam-size monitor using optical diffraction radiation techniques during top-up injection will also be addressed.

43 PARTICLE ACCELERATORS↗

Proposed Enhanced Imaging Station in the 6-GeV Booster-to-Storage Ring Transport Line for APS Upgrade

The high charge per micropulse of up to 17 nC in the booster to storage ring transport line for APS Upgrade will necessitate changes in the imaging station used to evaluate beam emittance in this key region. The original Chromox screen has recently been replaced by a YAG:Ce single crystal for immediate screen spatial resolution improvement down to <10 µm. However, the optical system also needs an upgrade with lenses and a digital camera to take full advantage of this. In addition, at the high areal charge densities expected, the YAG:Ce scintillator mechanism will saturate, or quench, leading to images larger than the actual beam size. To circumvent this effect, optical transition radiation (OTR) screens will be implemented. A proposed longer-range goal of a non-intercepting beam-size monitor using optical diffraction radiation techniques during top-up injection will also be addressed.

43 PARTICLE ACCELERATORS↗

Proposed Potential Mitigation of Wastewater Disposal Through Treated Produced Water in Bakken Formation

The recent global expansion in the development of unconventional oil and gas assets has also resulted in a tremendous increase in the number of extended horizontal drilling and hydraulic fracturing projects in the Bakken. The United States is presently the largest global crude oil producer, and the Bakken Formation in North Dakota is one of the major contributors to this achievement. However, the wastewater produced from these increased oilfield activities are highly saline (∼170,000 to 350,000 ppm TDS) and no technology currently available can satisfactorily treat it. As a result, more than 90% of wastewater in the Bakken is disposed of by deep injection into disposal wells. However, there are growing environmental and operational concerns about the sustainability and impacts of this approach. Research has shown that cumulative wastewater injection in some areas could increase the chances of earthquakes in those areas. However, if this produced water is efficiently treated, it could be reused in hydraulic fracturing operations or to support coal mining and irrigation activities. All these applications would reduce the need for wastewater injection and reduce the demand for fresh water used in hydraulic fracturing operations across North Dakota. For this purpose, we propose an enhanced supercritical technology we call Supercritical Water Extraction – Enhance Targeted Recovery to handle the issue of high TDS of flowback and produced water in the Bakken.

04 OIL SHALES AND TAR SANDS↗

Cadmium Telluride Photovoltaics Accelerator Consortium Solicitation: Request for Proposals Information

Cadmium telluride photovoltaics (CdTe PV) is a leading PV technology built on U.S. innovations that currently holds significant market share within domestic utility scale PV systems. In order to keep pace with a highly competitive and innovative global PV module market, CdTe manufacturing needs readily adaptable advances at the cell and module levels that simultaneously enable higher conversion efficiencies and manufacturing cost reductions without risking long-term module durability. In pursuit of this goal, the Department of Energy (DOE) Solar Energy Technologies Office (SETO) has asked the National Renewable Energy Laboratory (NREL) to launch and support a Consortium to accelerate domestic CdTe technology development through a competitive solicitation process. NREL will competitively select a CdTe Consortium with the goals of enhancing U.S. competitiveness and expanding domestic CdTe PV material and module production through 2030. NREL will provide coordination and oversight through development of technical scopes, review of technical proposals, subcontract support, and review of deliverables along with research support to the Consortium. The new Consortium is expected to include major U.S. companies and universities that possess strong technology development, transfer, and validation capabilities. The research and analysis output of the CdTe Consortium will inform purchasing, design, deployment, and operations decisions of companies in the domestic CdTe PV supply chain, leading to increased material and module production in the U.S.

41 EE - Solar Energy Technologies Office (EE-4S)↗

Collaborative Proposal: Improving Understanding of the Internal Structure and Dynamics of Deep Convection Using ARM Observations and Large Eddy Simulations (Final progress report)

This is the final technical report for the DOE Atmospheric System Research funded project entitled "Collaborative Proposal: Improving Understanding of the Internal Structure and Dynamics of Deep Convection Using ARM Observations and Large Eddy Simulations". This project addressed several science questions related to the structure and behavior of deep convective clouds in the atmosphere. It applied knowledge gained from this work to improve the deep cumulus convection parameterization in the Community Earth System Model (CESM). Specific outcomes related to the project include an improved understanding of: (1) how convective cloud environments regulate the size of thermals reaching the upper troposphere, and hence the shallow-to-deep convective transition; (2) the role of dynamic pressure forcing in thermal and convective cloud evolution; and (3) the role of vertical wind shear on the behavior of moist thermals and the transition from shallow to deep convection. Although the primary motivation of this project was to improve basic understanding of thermal dynamics in atmospheric convection, an important component of this work was using this improved understanding to modify the representation of entrainment and vertical velocity profiles in the Zhang-McFarlane cumulus parameterization used in CESM. This work also had a strong observational component, with analyses of Atmospheric Radiation Measurement (ARM) observations to characterize thermal characteristics and behavior. Observations collected during the ARM-supported CACTI field project were used with high-resolution simulations to explore environmental controls on deep convection initiation. Data from the ARM-supported MC3E field project were also used to evaluate the representation of updraft vertical velocities in the Zhang-McFarlane cumulus parameterization. This project directly supported the training of two post-doctoral researchers and led to 16 peer-reviewed published papers.

54 ENVIRONMENTAL SCIENCES↗

Siting and Transportation for Consolidated Used Nuclear Fuel Management Facilities: A Proposed Approach for a Regional Initiative to Begin the Dialogue - 13562

The Blue Ribbon Commission on America's Nuclear Future (BRC) was formed in January 2010 to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle, and to develop a new national strategy. Over two years, the BRC held dozens of meetings and heard from hundreds of Federal, State, Tribal, and local officials, as well as representatives of trade and labor organizations, technical groups, non-governmental organizations, and other stakeholders. The Commission's final report (issued January 26, 2012) offers a strategy to resolve longstanding challenges to responsible management of the United States' nuclear waste legacy. The Commission recommended Congressional action to rewrite parts of the Nuclear Waste Policy Act (NWPA); however, a comprehensive legislative overhaul will likely take years to fully implement. The nature and characteristics of nuclear waste, the activities that generated it, and the past history of federal efforts to manage the waste make it virtually certain that finding workable solutions will be controversial and difficult. As the BRC report suggests, this difficulty can be made insurmountable if top-down, federally-mandated efforts are forced upon unwilling States, Tribes, and local communities. Decades of effort and billions of ratepayer and taxpayer dollars have been spent attempting to site and operate spent fuel storage and disposal facilities in this manner. The experience thus far indicates that voluntary consent and active partnership of States, Tribes, and local governments in siting, designing, and operating such facilities are critical. Some States, Tribes, and local communities have indicated that, given adequate scientific and technical information, along with appropriate incentives, assurances, and authority, they might be willing to consider hosting facilities for consolidated storage and disposal of spent nuclear fuel. The authors propose a new regional approach to identifying and resolving issues related to the selection of a consolidated storage site. The approach would be characterized by informed discussion and deliberation, bringing together stakeholders from government, the non-governmental (NGO) community, industry, and other sectors. Because site selection would result in regional transportation impacts, the development of the transportation system (e.g., route identification, infrastructure improvements) would be integrated into the issue-resolution process. In addition to laying out the necessary steps and associated timeline, the authors address the challenges of building public trust and confidence in the new waste management program, as well as the difficulty of reaching and sustaining broad-based consensus on a decision to host a consolidated storage facility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Proposed Operations Master Plan of Cigeo - 17013

The proposed operations master plan of Cigeo describes the so-called 'reference progression' of the Cigeo project as envisaged by Andra at the end of the preliminary design studies. It aims at clarifying the objectives of the industrial pilot phase and present the choices offered by the reversibility for the management of the Cigeo project. The reference progression includes the inventory of the waste to be disposed of in Cigeo used for the dimensioning (73 600 m{sup 3} of ILW-LL and 10 100 m{sup 3} of HLW). Cigeo is designed to store the waste already produced and those that will be produced in the future by the existing nuclear installations and those whose creation was authorized, until the predictable end of their operation and their dismantling. All spent fuel is assumed to be reprocessed. The reference progression also includes the duration and the projected milestones of the construction and operation phases of Cigeo until termination. Across the operating life of Cigeo, the extensions of the Cigeo repository areas proceed by successive incremental phases, from the start of the industrial pilot phase (2025) to the final closure operations planned by 2150. Reversibility is defined as the ability to offer to the next generations different choices in terms of radioactive waste long-term management. The implementation of the reversibility principle is based on both governance and technical project management tools. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Proposal of a Descriptive Modeling of Portland Cement Behavior under Radioactive Waste Repository Environment - 17267

Storage and disposal of DSRS is a problem in many countries over the world. Brazilian inventory is about 300,000 sources (in use or stored), many of them with high activity and long lived radionuclides. Our proposal to deposition of DSRS: Dispose of the DSRS in a deep borehole repository. The IPEN concept was adapted from the BOSS Concept, developed by the NECSA/IAEA. Cementitious materials are intended to be used as a backfill material between the steel casing and the geological formation around the borehole and Casing. The required service life of the installation is counted in thousands of years. Issues to be addressed: Assessment of cement paste long-term durability and its behavior under radiation, high pressure and temperature and penetration of groundwater containing chemically aggressive species. The present study aims at defining the relevant external factors and their influence on the durability of hydrated cement. This study will be helpful on modeling the long-term reactions in the cement matrix and can improve the safety assessment. The synergism between all factors that can affect the cement is hard to predict and have to take into account many processes. For example, the calcium ion content in a cementitious matrix can be altered by many factors and depends on the cement mix designs and environmental factors that will prevail at the repository.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Evaluation of proposed Section III Division 5 Class B rules: Piping example problem

Evaluation of proposed Section III Division 5 Class B rules: Piping example problem to be presented include Z pipe geometry and model problem statement, Z pipe loads and design inputs problem statement, Primary Stress Limit overview, Primary stress limit pseudo yield stress calculation, Primary stress limited factored load procedure, Strain limit evaluation composite load cycle, Strain limit evaluation pseudo yield stress, Strain limit evaluation strain limit criteria and ratcheting check, Creep fatigue damage evaluation overview, Creep fatigue damage evaluation alternating stress calculations, Creep fatigue damage evaluation lower bound stress, Creep fatigue damage evaluation stress relaxation history, Creep fatigue damage evaluation damage fractions, and Recommendations to consider for Z-pipe problem.

42 ENGINEERING↗

Proposed Analytical Methods for Determining Filter Media Properties

High Efficiency Particulate Air (HEPA) filters, commonly used in nuclear filtration applications, are an integral part of the waste management processes in nuclear plants. HEPA filters are 99.97% efficient filtration devices characterized by their high resistance to air flow, or pressure drop. From theoretical models, the initial pressure drop across a clean filter is proven to be a function of the filter media fiber diameters and porosity of the media. These filter properties are relatively difficult to obtain with traditional manual methods; therefore, there is a need to develop analytical methods to find the fiber diameter and porosity to determine the pressure drop. Typically, these values can be found by substituting a calculated representative value based upon measured values, such as equivalent fiber diameter based upon a clean pressure drop. However, these values may also be directly recorded and measured by incorporating Scanning Electron Microscope (SEM) image analysis and other measurement methods to analyze the filter media and determine its physical properties without the need for media testing. DiameterJ, an open source Java plug-in, used with ImageJ, can process images of filter media taken by an SEM to find statistical data such as mean fiber diameter and porosity. To produce the raw data, SEM images of two filter media type samples are taken and segmented in DiameterJ using the traditional and statistical region merging segmentation algorithms. Manual segmentation is necessary after the initial segmentation by the algorithms as the images tend to be too complex for the algorithms to output with the necessary accuracy. However, complications exist in the manual segmentation process as these methods can be time intensive and prone to the individual bias of the user. This in turn can skew the final mean fiber diameter result, and lead to either an over or under prediction of the pressure drop. It was also discovered that the porosity data produced by DiameterJ is inaccurate, as the SEM analyzes the three-dimensional filter media by projecting its geometry onto a plane and analyzing it as a two-dimensional binary image. Thus, the porosity is artificially inflated through the segmentation process, rendering this result incorrect. Alternatively, density determination, gravimetric analysis, and thickness testing of the filter media is collectively used to determine the filter fiber porosity. Together, the SEM image analysis and analytical lab methods produce results through direct measurements which allow for the prediction of the initial pressure drop from clean filter media without the need for prior media testing to collect pressure data. By improving upon this proposed analytical method in the future, there is potential to streamline the process of finding these filter properties into a more direct methodology for determining the pressure drop across HEPA filters.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

RISMC Analysis Framework in Response to Proposed 10 CFR 50.46c Rulemaking

The results obtained from the demonstration calculations indicate that as an automation tool in LOCA analyses, LOTUS has the capability to provide integrated evaluation through seamless interfaces of the data stream in multiple disciplines. With further more development, LOTUS will provide a systematic way to perform uncertainty quantification, sensitivity analysis and risk assessment of the multiple physics involved in the LOCA analysis in response to the proposed 10 CFR 50.46c rulemaking. It can be used to obtain quantitative estimate of design or operational margin loss or gain as well as to assess the impact on LOCA analysis safety metrics associated with various combinations of changes in LOCA analysis inputs. It can also aid plant owners to make decision on evaluating design changes as well as resolving operational issues. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

ADVANTG Results for a Proposed NDA System for Detecting Pin Diversion from SNF - Paper 120

This summary describes the results of applying the ADVANTG variance reduction parameter generator to accelerate continuous-energy Monte Carlo simulations of the {sup 252}Cf Interrogation with Prompt Neutron (CIPN) detection system proposed by Hu et al. for detecting the diversion of fuel elements from spent nuclear fuel (SNF) assemblies. In previous work, ADVANTG was applied to a suite of nine radiation detection, special nuclear material (SNM) movement detection, and safeguards test cases. That effort demonstrated that ADVANTG was able to provide large increases in tally figures of merit (FOMs) in nearly all of the cases without introducing bias into the Monte Carlo results. The objective of the work described here is to further evaluate ADVANTG, and also to identify gaps in capability with regard to nuclear safeguards applications, by applying the code to a challenging problem that is of a different nature from the ones previously studied. The CIPN nondestructive assay (NDA) system consists of three fission chambers embedded in a C-shaped block of polyethylene and a polyethylene-moderated {sup 252}Cf source that are placed on opposite sides of a subject SNF assembly. The idea of the detection system is to measure the difference between the background neutron count rate, due to spontaneous fission in the fuel material, and the count rate observed once the source is introduced, which is dominated by multiplication within the assembly. Based on the difference between these count rates, the fissile content of the assembly can be inferred, and this information can be used to determine if some fraction of the original fuel pins have been replaced with depleted uranium substitutes. The authors report that the system can detect the replacement of at least eight pins (3% of total mass). The ADVANTG code generates space- and energy-dependent weight-window bounds and biased source distributions based on approximate transport solutions that are efficiently generated by the Denovo 3-D discrete ordinates package. ADVANTG implements the Consistent Adjoint Driven Importance Sampling (CADIS) method for accelerating individual tallies and the Forward-Weighted CADIS (FW-CADIS) method for obtaining relatively uniform uncertainties across tallies over multiple regions and/or energy bins. The variance reduction parameters are generated in a format directly usable by standard versions of MCNP5 and MCNPX. In this work, the ADVANTG variance reduction parameter generator was applied to accelerate continuous energy MCNPX simulations of the {sup 252}Cf Interrogation with Prompt Neutron detection system for detecting the diversion of fuel elements from SNF assemblies. Variance reduction parameters generated with the existing version of ADVANTG actually slowed down tally convergence in all cases. The cause of the poor performance was found to be the lack of an induced fission source treatment in the fixed-source discrete ordinates calculations employed by ADVANTG. Because fission was treated as capture and not as a source, the importance maps generated by ADVANTG significantly underestimated the importance of thermal neutrons in and around the fuel elements. In order to obtain improved results, we developed an experimental implementation of a fission source outer iteration for the adjoint calculations. We used this prototype capability to generate new variance reduction parameters and found that the mean fission rates agreed well with those predicted by the conventional MCNPX simulations, as was expected. With these new parameters, speedup factors of 59 to 80 were obtained for the case with the background source, and factors of 17 to 24 were obtained for the cases with the interrogating source. These results demonstrate that a fission source treatment is needed to improve the effectiveness of ADVANTG in problems where the effects of induced fission are important. This includes many types of NDA problems that are relevant to safeguards applications. (authors)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

A Proposal for a Three Detector Short-Baseline Neutrino Oscillation Program in the Fermilab Booster Neutrino Beam

A Short-Baseline Neutrino (SBN) physics program of three LAr-TPC detectors located along the Booster Neutrino Beam (BNB) at Fermilab is presented. This new SBN Program will deliver a rich and compelling physics opportunity, including the ability to resolve a class of experimental anomalies in neutrino physics and to perform the most sensitive search to date for sterile neutrinos at the eV mass-scale through both appearance and disappearance oscillation channels. Using data sets of 6.6e20 protons on target (P.O.T.) in the LAr1-ND and ICARUS T600 detectors plus 13.2e20 P.O.T. in the MicroBooNE detector, we estimate that a search for muon neutrino to electron neutrino appearance can be performed with ~5 sigma sensitivity for the LSND allowed (99% C.L.) parameter region. In this proposal for the SBN Program, we describe the physics analysis, the conceptual design of the LAr1-ND detector, the design and refurbishment of the T600 detector, the necessary infrastructure required to execute the program, and a possible reconfiguration of the BNB target and horn system to improve its performance for oscillation searches.

43 PARTICLE ACCELERATORS↗

Proposal for grid computing for nuclear applications

The use of computer clusters for computational sciences including computational physics is vital as it provides computing power to crunch big numbers at a faster rate. In compute intensive applications that requires high resolution such as Monte Carlo simulation, the use of computer clusters in a grid form that supplies computational power to any nodes within the grid that needs computing power, has now become a necessity. In this paper, we described how the clusters running on a specific application could use resources within the grid, to run the applications to speed up the computing process.

97 MATHEMATICS AND COMPUTING↗

Use Restriction (UR) Update Activity, Groups 23 and 31 URs Proposed for Downgrade or Removal

A White Paper document containing background information, rationale, and conclusion as justification for the downgrade or removal of use restrictions from various FFACO Corrective Action Sites (CASs) and their associated Corrective Action Units (CAUs) at the Nevada National Security Site (NNSS) [previously Nevada Test Site (NTS), as referred to throughout the white paper].

54 ENVIRONMENTAL SCIENCES↗