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Addendum to the Building America House Simulation Protocols (open access)

Addendum to the Building America House Simulation Protocols

As Building America (BA) has grown to include a large and diverse cross-section of the home building and retrofit industries, it has become more important to develop accurate, consistent analysis techniques to measure progress towards the program's goals. The House Simulation Protocols (HSP) provides guidance to program partners and managers so that energy savings for new construction and retrofit projects can be compared alongside each other. The HSP provides the program with analysis methods that are proven to be effective and reliable in investigating the energy use of advanced energy systems and of entire houses.
Date: December 1, 2012
Creator: Engebrecht-Metzger, C.; Wilson, E. & Horowitz, S.
Object Type: Report
System: The UNT Digital Library
Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters Nevada National Security Site, Nevada, Revision 0 (open access)

Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters Nevada National Security Site, Nevada, Revision 0

This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters, Nevada Test Site, Nevada (Revision 0), April 2011.
Date: January 1, 2012
Creator: Sloop, Patrick Matthews and Christy
Object Type: Report
System: The UNT Digital Library
Adiabatic capture and debunching (open access)

Adiabatic capture and debunching

In the study of beam preparation for the g-2 experiment, adiabatic debunching and adiabatic capture are revisited. The voltage programs for these adiabbatic processes are derived and their properties discussed. Comparison is made with some other form of adiabatic capture program. The muon g-2 experiment at Fermilab calls for intense proton bunches for the creation of muons. A booster batch of 84 bunches is injected into the Recycler Ring, where it is debunched and captured into 4 intense bunches with the 2.5-MHz rf. The experiment requires short bunches with total width less than 100 ns. The transport line from the Recycler to the muon-production target has a low momentum aperture of {approx} {+-}22 MeV. Thus each of the 4 intense proton bunches required to have an emittance less than {approx} 3.46 eVs. The incoming booster bunches have total emittance {approx} 8.4 eVs, or each one with an emittance {approx} 0.1 eVs. However, there is always emittance increase when the 84 booster bunches are debunched. There will be even larger emittance increase during adiabatic capture into the buckets of the 2.5-MHz rf. In addition, the incoming booster bunches may have emittances larger than 0.1 eVs. In this article, we will concentrate …
Date: March 1, 2012
Creator: Ng, K. Y.
Object Type: Report
System: The UNT Digital Library
Adjoint based a posteriori error estimation in Drekar::CFD. (open access)

Adjoint based a posteriori error estimation in Drekar::CFD.

None
Date: October 1, 2012
Creator: Wildey, Timothy Michael; Cyr, Eric C.; Pawlowski, Roger Patrick; Shadid, John Nicolas & Smith, Thomas Michael
Object Type: Report
System: The UNT Digital Library
Adjustable Speed Drive Part-Load Efficiency, Motor Systems Tip Sheet #11 (Fact Sheet) (open access)

Adjustable Speed Drive Part-Load Efficiency, Motor Systems Tip Sheet #11 (Fact Sheet)

Motor tip sheet for the Advanced Manufacturing Office.
Date: November 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
AN ADVANCED CALIBRATION PROCEDURE FOR COMPLEX IMPEDANCE SPECTRUM MEASUREMENTS OF ADVANCED ENERGY STORAGE DEVICES (open access)

AN ADVANCED CALIBRATION PROCEDURE FOR COMPLEX IMPEDANCE SPECTRUM MEASUREMENTS OF ADVANCED ENERGY STORAGE DEVICES

With the increasing demand for electric and hybrid electric vehicles and the explosion in popularity of mobile and portable electronic devices such as laptops, cell phones, e-readers, tablet computers and the like, reliance on portable energy storage devices such as batteries has likewise increased. The concern for the availability of critical systems in turn drives the availability of battery systems and thus the need for accurate battery health monitoring has become paramount. Over the past decade the Idaho National Laboratory (INL), Montana Tech of the University of Montana (Tech), and Qualtech Systems, Inc. (QSI) have been developing the Smart Battery Status Monitor (SBSM), an integrated battery management system designed to monitor battery health, performance and degradation and use this knowledge for effective battery management and increased battery life. Key to the success of the SBSM is an in-situ impedance measurement system called the Impedance Measurement Box (IMB). One of the challenges encountered has been development of an accurate, simple, robust calibration process. This paper discusses the successful realization of this process.
Date: June 1, 2012
Creator: Morrison, William H.; Christophersen, Jon P.; Bald, Patrick & Morrison, John L.
Object Type: Article
System: The UNT Digital Library
Advanced Control and Protection system Design Methods for Modular HTGRs (open access)

Advanced Control and Protection system Design Methods for Modular HTGRs

The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regulatory implications concerning the control and protection systems proposed for use in the Department of Energy's (DOE) Next-Generation Nuclear Plant (NGNP). The NGNP, using modular high-temperature gas-cooled reactor (HTGR) technology, is to provide commercial industries with electricity and high-temperature process heat for industrial processes such as hydrogen production. Process heat temperatures range from 700 to 950 C, and for the upper range of these operation temperatures, the modular HTGR is sometimes referred to as the Very High Temperature Reactor or VHTR. Initial NGNP designs are for operation in the lower temperature range. The defining safety characteristic of the modular HTGR is that its primary defense against serious accidents is to be achieved through its inherent properties of the fuel and core. Because of its strong negative temperature coefficient of reactivity and the capability of the fuel to withstand high temperatures, fast-acting active safety systems or prompt operator actions should not be required to prevent significant fuel failure and fission product release. The plant is designed such that its inherent features should provide adequate protection despite operational errors or equipment failure. Figure 1 shows an example modular HTGR …
Date: June 1, 2012
Creator: Ball, Sydney J.; Wilson, Thomas L., Jr. & Wood, Richard Thomas
Object Type: Report
System: The UNT Digital Library
Advanced Design Studies. Final report (open access)

Advanced Design Studies. Final report

The ARIES-CS project was a multi-year multi-institutional project to assess the feasibility of a compact stellarator as a fusion power plant. The work herein describes efforts to help design one aspect of the device, the divertor, which is responsible for the removal of particle and heat flux from the system, acting as the first point of contact between the magnetically confined hot plasma and the outside world. Specifically, its location and topology are explored, extending previous work on the sub ject. An optimized design is determined for the thermal particle flux using a suite of 3D stellarator design codes which trace magnetic field lines from just inside the confined plasma edge to their strike points on divertor plates. These divertor plates are specified with a newly developed plate design code. It is found that a satisfactory thermal design exists which maintains the plate temperature and heat load distribution below tolerable engineering limits. The design is unique, including a toroidal taper on the outboard plates which was found to be important to our results. The maximum thermal heat flux for the final design was 3.61 M W/m2 and the maximum peaking factor was 10.3, below prescribed limits of 10 M W/m2 …
Date: December 1, 2012
Creator: Steiner, Don
Object Type: Report
System: The UNT Digital Library
Advanced Energy Design Guides Slash Energy Use in Schools and Retail Buildings by 50% (Fact Sheet) (open access)

Advanced Energy Design Guides Slash Energy Use in Schools and Retail Buildings by 50% (Fact Sheet)

Owners, contractors, engineers, and architects can easily achieve significant energy savings by leveraging the complex analyses and expertise captured in these guides.
Date: April 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Energy Industries, Inc. SEGIS developments. (open access)

Advanced Energy Industries, Inc. SEGIS developments.

The Solar Energy Grid Integration Systems (SEGIS) initiative is a three-year, three-stage project that includes conceptual design and market analysis (Stage 1), prototype development/testing (Stage 2), and commercialization (Stage 3). Projects focus on system development of solar technologies, expansion of intelligent renewable energy applications, and connecting large-scale photovoltaic (PV) installations into the electric grid. As documented in this report, Advanced Energy Industries, Inc. (AE), its partners, and Sandia National Laboratories (SNL) successfully collaborated to complete the final stage of the SEGIS initiative, which has guided new technology development and development of methodologies for unification of PV and smart-grid technologies. The combined team met all deliverables throughout the three-year program and commercialized a broad set of the developed technologies.
Date: March 1, 2012
Creator: Scharf, Mesa P. (Advanced Energy Industries, Inc., Bend, OR); Bower, Ward Isaac; Mills-Price, Michael A. (Advanced Energy Industries, Inc., Bend, OR); Sena-Henderson, Lisa; David, Carolyn; Akhil, Abbas Ali et al.
Object Type: Report
System: The UNT Digital Library
Advanced Energy Storage Life and Health Prognostics (INL) FY 2012 Annual Progress Report (open access)

Advanced Energy Storage Life and Health Prognostics (INL) FY 2012 Annual Progress Report

The objective of this work is to develop methodologies that will accurately estimate state-of-health (SOH) and remaining useful life (RUL) of electrochemical energy storage devices using both offline and online (i.e., in-situ) techniques through: · A statistically robust offline battery calendar life estimator tool based on both testing and simulation, and · Novel onboard sensor technology for improved online battery diagnostics and prognostics.
Date: October 1, 2012
Creator: Christophersen, Jon P.
Object Type: Report
System: The UNT Digital Library
Advanced Fuels Campaign 2012 Accomplishments (open access)

Advanced Fuels Campaign 2012 Accomplishments

The Advanced Fuels Campaign (AFC) under the Fuel Cycle Research and Development (FCRD) program is responsible for developing fuels technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. The fiscal year 2012 (FY 2012) accomplishments are highlighted below. Kemal Pasamehmetoglu is the National Technical Director for AFC.
Date: November 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Fuels for LWRs: Fully-Ceramic Microencapsulated and Related Concepts FY 2012 Interim Report (open access)

Advanced Fuels for LWRs: Fully-Ceramic Microencapsulated and Related Concepts FY 2012 Interim Report

This report summarizes the progress in the Deep Burn project at Idaho National Laboratory during the first half of fiscal year 2012 (FY2012). The current focus of this work is on Fully-Ceramic Microencapsulated (FCM) fuel containing low-enriched uranium (LEU) uranium nitride (UN) fuel kernels. UO2 fuel kernels have not been ruled out, and will be examined as later work in FY2012. Reactor physics calculations confirmed that the FCM fuel containing 500 mm diameter kernels of UN fuel has positive MTC with a conventional fuel pellet radius of 4.1 mm. The methodology was put into place and validated against MCNP to perform whole-core calculations using DONJON, which can interpolate cross sections from a library generated using DRAGON. Comparisons to MCNP were performed on the whole core to confirm the accuracy of the DRAGON/DONJON schemes. A thermal fluid coupling scheme was also developed and implemented with DONJON. This is currently able to iterate between diffusion calculations and thermal fluid calculations in order to update fuel temperatures and cross sections in whole-core calculations. Now that the DRAGON/DONJON calculation capability is in place and has been validated against MCNP results, and a thermal-hydraulic capability has been implemented in the DONJON methodology, the work will …
Date: March 1, 2012
Creator: Sen, R. Sonat; Boer, Brian; Bess, John D.; Pope, Michael A. & Ougouag, Abderrafi M.
Object Type: Report
System: The UNT Digital Library
Advanced High-Speed 16-Bit Digitizer System (open access)

Advanced High-Speed 16-Bit Digitizer System

The fastest commercially available 16-bit ADC can only perform around 200 mega-samples per second (200 MS/s). Connecting ADC chips together in eight different time domains increases the quantity of samples taken by a factor of eight. This method of interleaving requires that the input signal being sampled is split into eight identical signals and arrives at each ADC chip at the same point in time. The splitting of the input signal is performed in the analog front end containing a wideband filter that impedance matches the input signal to the ADC chips. Each ADC uses a clock to tell it when to perform a conversion. Using eight unique clocks spaced in 45-degree increments is the method used to time shift when each ADC chip performs its conversion. Given that this control clock is a fixed frequency, the clock phase shifting is accomplished by tightly controlling the distance that the clock must travel, resulting in a time delay. The interleaved ADC chips will now generate digital data in eight different time domains. These data are processed inside a field-programmable gate array (FPGA) to move the data back into a single time domain and store it into memory. The FPGA also contains …
Date: May 1, 2012
Creator: unknown
Object Type: Article
System: The UNT Digital Library
Advanced inactive materials for improved lithium-ion battery safety. (open access)

Advanced inactive materials for improved lithium-ion battery safety.

None
Date: November 1, 2012
Creator: Orendorff, Christopher J.; Nagasubramanian, Ganesan; Lambert, Timothy N.; Fenton, Kyle Ross; Apblett, Christopher Alan; Shaddix, Christopher R. et al.
Object Type: Report
System: The UNT Digital Library
Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan (open access)

Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan

Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.
Date: September 1, 2012
Creator: Hallbert, Bruce
Object Type: Report
System: The UNT Digital Library
Advanced Low-Cost Receivers for Parabolic Troughs (Fact Sheet) (open access)

Advanced Low-Cost Receivers for Parabolic Troughs (Fact Sheet)

Norwich Technologies is one of the 2012 SunShot CSP R&D awardees for their advanced receivers. This fact sheet explains the motivation, description, and impact of the project.
Date: September 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study (open access)

Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.
Date: September 1, 2012
Creator: Barrett, Kristine & Bragg-Sitton, Shannon
Object Type: Report
System: The UNT Digital Library
Advanced Manufacture of Reflectors (Fact Sheet) (open access)

Advanced Manufacture of Reflectors (Fact Sheet)

The University of Arizona is one of the 2012 SunShot CSP R&D awardees for their advanced collectors. This fact sheet explains the motivation, description, and impact of the project.
Date: September 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Manufacturing for a U.S. Clean Energy Economy (Fact Sheet) (open access)

Advanced Manufacturing for a U.S. Clean Energy Economy (Fact Sheet)

This fact sheet is an overview of the U.S. Department of Energy's Advanced Manufacturing Office. Manufacturing is central to our economy, culture, and history. The industrial sector produces 11% of U.S. gross domestic product (GDP), employs 12 million people, and generates 57% of U.S. export value. However, U.S. industry consumes about one-third of all energy produced in the United States, and significant cost-effective energy efficiency and advanced manufacturing opportunities remain unexploited. As a critical component of the National Innovation Policy for Advanced Manufacturing, the U.S. Department of Energy's (DOE's) Advanced Manufacturing Office (AMO) is focused on creating a fertile environment for advanced manufacturing innovation, enabling vigorous domestic development of transformative manufacturing technologies, promoting coordinated public and private investment in precompetitive advanced manufacturing technology infrastructure, and facilitating the rapid scale-up and market penetration of advanced manufacturing technologies.
Date: March 1, 2012
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Measurements of Silicon Carbide Ceramic Matrix Composites (open access)

Advanced Measurements of Silicon Carbide Ceramic Matrix Composites

Silicon carbide (SiC) is being considered as a fuel cladding material for accident tolerant fuel under the Light Water Reactor Sustainability (LWRS) Program sponsored by the Nuclear Energy Division of the Department of Energy. Silicon carbide has many potential advantages over traditional zirconium based cladding systems. These include high melting point, low susceptibility to corrosion, and low degradation of mechanical properties under neutron irradiation. In addition, ceramic matrix composites (CMCs) made from SiC have high mechanical toughness enabling these materials to withstand thermal and mechanical shock loading. However, many of the fundamental mechanical and thermal properties of SiC CMCs depend strongly on the fabrication process. As a result, extrapolating current materials science databases for these materials to nuclear applications is not possible. The “Advanced Measurements” work package under the LWRS fuels pathway is tasked with the development of measurement techniques that can characterize fundamental thermal and mechanical properties of SiC CMCs. An emphasis is being placed on development of characterization tools that can used for examination of fresh as well as irradiated samples. The work discuss in this report can be divided into two broad categories. The first involves the development of laser ultrasonic techniques to measure the elastic and …
Date: August 1, 2012
Creator: Farzbod, Farhad; Reese, Stephen J.; Hua, Zilong; Khafizov, Marat & Hurley, David H.
Object Type: Report
System: The UNT Digital Library
Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities (open access)

Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities

The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work …
Date: May 1, 2012
Creator: Weatherby, Gregory
Object Type: Report
System: The UNT Digital Library
Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report (open access)

Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report

An alternatives analysis was performed for the Advanced Post-Irradiation Capabilities (APIEC) project in accordance with the U.S. Department of Energy (DOE) Order DOE O 413.3B, “Program and Project Management for the Acquisition of Capital Assets”. The Alternatives Analysis considered six major alternatives: ? No Action ? Modify Existing DOE Facilities – capabilities distributed among multiple locations ? Modify Existing DOE Facilities – capabilities consolidated at a few locations ? Construct New Facility ? Commercial Partnership ? International Partnerships Based on the alternatives analysis documented herein, it is recommended to DOE that the advanced post-irradiation examination capabilities be provided by a new facility constructed at the Materials and Fuels Complex at the Idaho National Laboratory.
Date: December 1, 2012
Creator: Bryan, Jeff; Landman, Bill & Hill, Porter
Object Type: Report
System: The UNT Digital Library
Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2012 (open access)

Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2012

Legacy computational reactor physics software tools and protocols currently used for support of Advanced Test Reactor (ATR) core fuel management and safety assurance, and to some extent, experiment management, are inconsistent with the state of modern nuclear engineering practice, and are difficult, if not impossible, to properly verify and validate (V&V) according to modern standards. Furthermore, the legacy staff knowledge required for application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. In late 2009, the Idaho National Laboratory (INL) initiated a focused effort, the ATR Core Modeling Update Project, to address this situation through the introduction of modern high-fidelity computational software and protocols. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF). The ATR Core Modeling Update Project, targeted for full implementation in phase with the next anticipated ATR Core Internals Changeout (CIC) in the 2014-2015 time frame, began during the last quarter of Fiscal Year …
Date: September 1, 2012
Creator: David W. Nigg, Principal Investigator & Kevin A. Steuhm, Project Manager
Object Type: Report
System: The UNT Digital Library