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385 Matching Results
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Aerothermodynamics, Comprehensive Technical Report, Direct Air Cycle, General Electric's Air Craft Nuclear Propulsion Program
This is one of twenty-one volumes summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume summarizes the methods and techquies developed for use in the thermal design of nuclear reactors associated with that program.
Date:
December 6, 1961
Creator:
Noyes, R. N.
Object Type:
Report
System:
The UNT Digital Library
Toxic substances from coal combustion -- Forms of occurrence analyses. Technical progress report, April 30--November 1, 1996
The overall objective of this project is to provide analytical support for the Physical Sciences, Inc. (PSI) effort being performed under a DOE Contract. The Pittsburgh, Elkhorn/Hazard, and Illinois No. 6 program coals have been examined to determine the mode of occurrence of selected trace elements using scanning electron microscopy, microprobe analysis, and experimental leaching procedures. Preliminary microprobe data indicates that the arsenic content of pyrite grains in the Illinois No. 6 (0.0--0.027 ppm As) and Pittsburgh (0.0--0.080 ppm As) coals is similar. Pyrite grains observed in the Elkhorn/Hazard coal generally have arsenic concentrations (0.0--0.272 wt.% As) that are slightly higher than those of the Pittsburgh or Illinois No. 6 coals. One pyrite grain observed in the Elkhorn/Hazard coal contained much higher levels of arsenic (approximately 2 wt.% As). Preliminary microprobe analyses and data from leaching experiments indicate the association of arsenic with pyrite in the Pittsburgh and Illinois No. 6 coals. Leaching data for arsenic in the Elkhorn/Hazard coal, in contrast, is inconclusive and additional data are needed before a definite determination can be made.
Date:
December 6, 1996
Creator:
Crowley, Sharon S.; Palmer, Curtis A.; Kolker, Allan; Finkelman, Robert B.; Kolb, Kathleen C. & Belkin, Harvey E.
Object Type:
Report
System:
The UNT Digital Library
Corrective Action Investigation Plan for Corrective Action Unit 527: Horn Silver Mine, Nevada Test Site, Nevada: Revision 1 (Including Records of Technical Change No.1, 2, 3, and 4)
This Corrective Action Investigation Plan contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 527, Horn Silver Mine, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 527 consists of one Corrective Action Site (CAS): 26-20-01, Contaminated Waste Dump No.1. The site is located in an abandoned mine site in Area 26 (which is the most arid part of the NTS) approximately 65 miles northwest of Las Vegas. Historical documents may refer to this site as CAU 168, CWD-1, the Wingfield mine (or shaft), and the Wahmonie mine (or shaft). Historical documentation indicates that between 1959 and the 1970s, nonliquid classified material and unclassified waste was placed in the Horn Silver Mine's shaft. Some of the waste is known to be radioactive. Documentation indicates that the waste is present from 150 feet to the bottom of the mine (500 ft below ground surface). This CAU is being investigated because hazardous constituents migrating from materials and/or wastes disposed of in the Horn Silver Mine may pose a threat to human …
Date:
December 6, 2002
Creator:
U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office
Object Type:
Report
System:
The UNT Digital Library
Flexible manufacturing for photonics device assembly
The assembly of photonics devices such as laser diodes, optical modulators, and opto-electronics multi-chip modules (OEMCM), usually requires the placement of micron size devices such as laser diodes, and sub-micron precision attachment between optical fibers and diodes or waveguide modulators (usually referred to as pigtailing). This is a very labor intensive process. Studies done by the opto-electronics (OE) industry have shown that 95% of the cost of a pigtailed photonic device is due to the use of manual alignment and bonding techniques, which is the current practice in industry. At Lawrence Livermore National Laboratory, we are working to reduce the cost of packaging OE devices through the use of automation. Our efforts are concentrated on several areas that are directly related to an automated process. This paper will focus on our progress in two of those areas, in particular, an automated fiber pigtailing machine and silicon micro-bench technology compatible with an automated process.
Date:
December 6, 1993
Creator:
Lu, Shin-yee; Pocha, M. D.; Strand, O. T. & Young, K. D.
Object Type:
Article
System:
The UNT Digital Library
OptiFit: Computer-Vision-Based Smartphone Application to Measure the Foot from Images and 3D Scans
Article asserts that the foot is a vital organ, as it stabilizes the impact forces between the human skeletal system and the ground. The authors present an instep girth measurement algorithm, and they used a pixel per metric algorithm for measurement; these algorithms were accordingly integrated with the application.
Date:
December 6, 2022
Creator:
Rafiq, Riyad Bin; Hoque, Kazi Miftahul; Kabir, Muhammad Ashad; Ahmed, Sayed & Laird, Craig
Object Type:
Article
System:
The UNT Digital Library
Health-Physics Monthly Information Report. October 1951
None
Date:
December 6, 1951
Creator:
Bradley, J. E. & Burbage, J. J.
Object Type:
Report
System:
The UNT Digital Library
Project W-151 flexible receiver radiation detector system acceptance test plan. Revision 1
The attached document is the Acceptance Test Plan for the portion of Project W-151 dealing with acceptance of gamma-ray detectors and associated electronics manufactured at the Idaho National Engineering Laboratory (INEL). The document provides a written basis for testing the detector system, which will take place in the 305 building (300 Area).
Date:
December 6, 1994
Creator:
Troyer, G. L.
Object Type:
Report
System:
The UNT Digital Library
Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility
This report examines the contributing factors to NDA measurement uncertainty at WRAP. The significance of each factor on the TMU is analyzed, and a final method is given for determining the TMU for NDA measurements at WRAP. As more data becomes available, and WRAP gains in operational experience, this report will be reviewed semi-annually and updated as necessary.
Date:
December 6, 1999
Creator:
WILLS, C.E.
Object Type:
Report
System:
The UNT Digital Library
Pointing Control Design for a High Precision Flight Telescope Using Quantitative Feedback Theory
None
Date:
December 6, 2000
Creator:
Bentley, Anthony E.
Object Type:
Article
System:
The UNT Digital Library
Development of a Steady State Simulation Code for Klystron Amplifiers
None
Date:
December 6, 2012
Creator:
Marrelli, C.; Spataro, B.; Migliorati, M.; Mostacci, A.; Palumbo, L. & Tantawi, S.G.
Object Type:
Article
System:
The UNT Digital Library
Geologic Repository Plan for Disposal of Pu-Containing and Other Radioactive Materials in Russia
None
Date:
December 6, 2001
Creator:
Jardine, L
Object Type:
Report
System:
The UNT Digital Library
Mechanical Properties of K Basin Sludge Constituents and Their Surrogates
A survey of the technical literature was performed to summarize the mechanical properties of inorganic components in K Basins sludge. The components included gibbsite, ferrihydrite, lepidocrocite and goethite, hematite, quartz, anorthite, calcite, basalt, Zircaloy, aluminum, and, in particular, irradiated uranium metal and uranium dioxide. Review of the technical literature showed that information on the hardness of uranium metal at irradiation exposures similar to those experienced by the N Reactor fuel present in the K Basins (typically up to 3000 MWd/t) were not available. Measurements therefore were performed to determine the hardness of coupons taken from three irradiated N Reactor uranium metal fuel elements taken from K Basins. Hardness values averaged 30 {+-} 8 Rockwell C units, similar to values previously reported for uranium irradiated to {approx}1200 MWd/t. The physical properties of candidate uranium metal and uranium dioxide surrogates were gathered and compared. Surrogates having properties closest to those of irradiated uranium metal appear to be alloys of tungsten. The surrogate for uranium dioxide, present both as particles and agglomerates in actual K Basin sludge, likely requires two materials. Cerium oxide, CeO2, was identified as a surrogate of the smaller UO2 particles while steel grit was identified for the UO2 agglomerates.
Date:
December 6, 2004
Creator:
Delegard, Calvin H.; Schmidt, Andrew J. & Chenault, Jeffrey W.
Object Type:
Report
System:
The UNT Digital Library
Strength Measurements of Archive K Basin Sludge Using a Soil Penetrometer
Spent fuel radioactive sludge present in the K East and K West spent nuclear fuel storage basins now resides in the KW Basin in six large underwater engineered containers. The sludge will be dispositioned in two phases under the Sludge Treatment Project: (1) hydraulic retrieval into sludge transport and storage containers (STSCs) and transport to interim storage in Central Plateau and (2) retrieval from the STSCs, treatment, and packaging for shipment to the Waste Isolation Pilot Plant. In the years the STSCs are stored, sludge strength is expected to increase through chemical reaction, intergrowth of sludge crystals, and compaction and dewatering by settling. Increased sludge strength can impact the type and operation of the retrieval equipment needed prior to final sludge treatment and packaging. It is important to determine whether water jetting, planned for sludge retrieval from STSCs, will be effective. Shear strength is a property known to correlate with the effectiveness of water jetting. Accordingly, the unconfined compressive strengths (UCS) of archive K Basin sludge samples and sludge blends were measured using a pocket penetrometer modified for hot cell use. Based on known correlations, UCS values can be converted to shear strengths. Twenty-six sludge samples, stored in hot cells …
Date:
December 6, 2011
Creator:
Delegard, Calvin H.; Schmidt, Andrew J. & Chenault, Jeffrey W.
Object Type:
Report
System:
The UNT Digital Library
Production Test IP-467-C reducing minimum downtime
The objective of the Production Tests described in this report is to evaluate the operational aspects of a proposed method for reducing minimum downtime. The excess xenon poisoning, which occurs during the first 32--38 hours after the shutdown of a reactor from present equilibrium levels, will be partially overridden by a central enriched zone whose added reactivity contribution would be compensated during normal operation by means of poison splines. The test will be performed at B Reactor.
Date:
December 6, 1961
Creator:
Jaklevick, J. F.
Object Type:
Report
System:
The UNT Digital Library
Norfolk-Peninsula Area (ARMS-II)
From Introduction: "The ARMS-II Norfolk - Peninsula area survey was one many that have been flown for the CETO since the nationwide ARMS program was started (1958). Figure 2 shows the location of the areas that have been completed to date. The purpose of the program is to measure the present environmental levels of gamma radiation in areas around nuclear facilities and planned nuclear activities."
Date:
December 6, 1961
Creator:
Guillou, R. B.
Object Type:
Report
System:
The UNT Digital Library
Structural evaluation of thermocouple probes for 241-AZ-101 waste tank
This document reports on the structural analysis of the thermocouple probe to be installed in 241-AZ-101 waste tank. The thermocouple probe is analyzed for normal pump mixing operation and potential earthquake induced loads required by the Hanford Site Design Criteria SDC-4.1.
Date:
December 6, 1994
Creator:
Kanjilal, S. K.
Object Type:
Report
System:
The UNT Digital Library
The Role of Quantum Mechanics in Neutrino Factories.
A compilation is made of the various ways in which quantum phenomena enter into the design and operation of a neutrino factory. They include production of pions, decay of pions into muons, ionization energy loss of muons in material, scattering and energy straggling of muons in material, polarization of muons, and the decay of muons into neutrinos, and the radiation effect of neutrinos. For each process formulas are presented which cover the basic mechanism. A discussion is presented of the areas of uncertainty and of the experiments, underway and proposed, which will reduce the uncertainty to an acceptable level.
Date:
December 6, 2000
Creator:
Gallardo, J. C.; Sessler, A. M. & Wurtele, J.
Object Type:
Article
System:
The UNT Digital Library
Fire hazards analysis for the uranium oxide (UO{sub 3}) facility
The Fire Hazards Analysis (FHA) documents the deactivation end-point status of the UO{sub 3} complex fire hazards, fire protection and life safety systems. This FHA has been prepared for the Uranium Oxide Facility by Westinghouse Hanford Company in accordance with the criteria established in DOE 5480.7A, Fire Protection and RLID 5480.7, Fire Protection. The purpose of the Fire Hazards Analysis is to comprehensively and quantitatively assess the risk from a fire within individual fire areas in a Department of Energy facility so as to ascertain whether the objectives stated in DOE Order 5480.7, paragraph 4 are met. Particular attention has been paid to RLID 5480.7, Section 8.3, which specifies the criteria for deactivating fire protection in decommission and demolition facilities.
Date:
December 6, 1994
Creator:
Wyatt, D. M.
Object Type:
Report
System:
The UNT Digital Library
Validation, Uncertainty, and Quantitative Reliability at Confidence (QRC)
This paper represents a summary of our methodology for Verification and Validation and Uncertainty Quantification. A graded scale methodology is presented and related to other concepts in the literature. We describe the critical nature of quantified Verification and Validation with Uncertainty Quantification at specified Confidence levels in evaluating system certification status. Only after Verification and Validation has contributed to Uncertainty Quantification at specified confidence can rational tradeoffs of various scenarios be made. Verification and Validation methods for various scenarios and issues are applied in assessments of Quantified Reliability at Confidence and we summarize briefly how this can lead to a Value Engineering methodology for investment strategy.
Date:
December 6, 2002
Creator:
Logan, R W & Nitta, C K
Object Type:
Article
System:
The UNT Digital Library
FY2002 P Well Activities Report
The P wells were installed in the late 80s as part of the SRP Baseline Hydrogeological Investigation for the purpose of updating and improving the current knowledge and understanding of the hydrogeological systems underlying the SRS. During the installation of the P well series wells, a total of more than 16,000 feet of unconsolidated geologic sediments were cored and are currently stored at the Core Facility and 129 wells were installed at eighteen widely spaced P well clusters. Each well cluster nominally consists of 8 observations wells screened at the water table down to the lower McQueen Branch aquifer (Middendorf Formation). The vertical distribution of the wells at each cluster not only provides information on the hydraulic head within each monitoring unit but also the vertical gradients between the different formations.
Date:
December 6, 2002
Creator:
Noonkester, J.V.
Object Type:
Report
System:
The UNT Digital Library
The determination of the solidification paths and the liquidus surface in the quasicrystalline region of the Al-Cu-Ru systems
Objective is to determine if conventional slow-growth methods will be successful for growing single quasicrystals in this system. Reaction schemes, isopleths, and a ternary liquidus diagram were constructed using DTA, XRD, microscopy, and energy dispersive spectroscopy. Results suggest a peak in the liquidus near the predicted compositions of Al{sub 65}Cu{sub 23}Ru{sub 12} or Al{sub 65}Cu{sub 20}Ru{sub 15} in the face-centered icosahedral phase field. Further study is needed to verify the existence of a congruently melting phase. There appears to be composition for which slow-growth methods will produce a single-quasicrystal. Directional solidification studies were done on 65Al25Cu10Ru.
Date:
December 6, 1995
Creator:
Haines, S.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Experimental Validation of LLNL Finite Element Codes for Nonlinear Seismic Simulations (Progress, Year 1 of 2)
Shake table tests were performed on a full-scale 7-story slice of a reinforced concrete building at UC San Diego between October 2005 and January 2006. The tests were performed on the NEES Large High-Performance Outdoor Shake Table (LHPOST) at the Engelkirk Structural Engineering Center of UCSD. The structure was subjected to four uniaxial earthquake ground motions of increasing amplitude. The accelerations measured at the base of the structure and the measured roof displacements have been provided by UCSD. Details of the building construction have also been provided by UCSD. The measured response of this structure was used to assess the capability of the homogenized rebar model in DYNA3D/ParaDyn [1,2] to simulate the seismic response of reinforced concrete structures. The homogenized rebar model is a composite version of the Karagozian & Case concrete model [3]. Work has been done to validate this material model for use in blast simulations, but seismic simulations require longer durations. The UCSD experiment provides full-scale data that can be used to validate seismic modeling capabilities.
Date:
December 6, 2006
Creator:
Alves, S W & Noble, C R
Object Type:
Report
System:
The UNT Digital Library
Reaching Grid Parity Using BP Solar Crystalline Silicon Technology: A Systems Class Application
The primary target market for this program was the residential and commercial PV markets, drawing on BP Solar's premium product and service offerings, brand and marketing strength, and unique routes to market. These two markets were chosen because: (1) in 2005 they represented more than 50% of the overall US PV market; (2) they are the two markets that will likely meet grid parity first; and (3) they are the two market segments in which product development can lead to the added value necessary to generate market growth before reaching grid parity. Federal investment in this program resulted in substantial progress toward the DOE TPP target, providing significant advancements in the following areas: (1) Lower component costs particularly the modules and inverters. (2) Increased availability and lower cost of silicon feedstock. (3) Product specifically developed for residential and commercial applications. (4) Reducing the cost of installation through optimization of the products. (5) Increased value of electricity in mid-term to drive volume increases, via the green grid technology. (6) Large scale manufacture of PV products in the US, generating increased US employment in manufacturing and installation. To achieve these goals BP Solar assembled a team that included suppliers of critical materials, …
Date:
December 6, 2010
Creator:
Cunningham, Daniel W.; Wohlgemuth, John; Carlson, David E.; Clark, Roger F.; Gleaton, Mark; Posbic, John P. et al.
Object Type:
Report
System:
The UNT Digital Library
Hanford Site Transuranic (TRU) Waste Certification Plan
As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The …
Date:
December 6, 2000
Creator:
GREAGER, T.M.
Object Type:
Report
System:
The UNT Digital Library