UNT Libraries Government Documents Department - 967 Matching Results

Search Results

100 Area electrical distribution fault and coordination report

Description: This report documents three-phase and line-to-ground fault values and time overcurrent coordination curves for the electrical utility distribution system located in the 100 Areas. Activities that may improve the coordination of the distribution system have also been identified. An evaluation of system coordination was performed. The results of this evaluation are listed in Appendix B. There are protective devices within the 100 Area distribution system that do not coordinate with one another throughout the Areas. There is also a mis-application of reclosing relays at the 100B Area. The impact of the mis-coordination and incorrect application of reclosing relays is that system selectivity is reduced. Equipment will still be protected against damaging currents, however more equipment will be de-energized than necessary during fault conditions. It is the opinion of the author of this report that the cases of mis-coordination listed above, and in Appendix B, do not significantly degrade the system protection system nor the reliability of the 100 Area distribution system. Therefore, immediate response to correct these problems is not recommended. However, a planned methodology, outlined in an Activity Plan, to correct these problems should be developed and implemented in the near future.
Date: September 23, 1994
Creator: Webber, J. J.

105-DR Large sodium fire facility soil sampling data evaluation report

Description: This report evaluates the soil sampling activities, soil sample analysis, and soil sample data associated with the closure activities at the 105-DR Large Sodium Fire Facility. The evaluation compares these activities to the regulatory requirements for meeting clean closure. The report concludes that there is no soil contamination from the waste treatment activities.
Date: January 23, 1996
Creator: Adler, J.G.

(129)Xe NMR of Mesoporous Silicas

Description: The porosities of three mesoporous silica materials were characterized with {sup 129}Xe NMR spectroscopy. The materials were synthesized by a sol-gel process with r = 0, 25, and 70% methanol by weight in an aqueous cetyltrimethylammonium bromide solution. Temperature dependent chemical shifts and spin lattice relaxation times reveal that xenon does not penetrate the pores of the largely disordered (r= 70%) silica. For both r = 0 and 25%, temperature dependent resonances corresponding to physisorbed xenon were observed. An additional resonance for the r = 25% sample was attributed to xenon between the disordered cylindrical pores. 2D NMR exchange experiments corroborate the spin lattice relaxation data which show that xenon is in rapid exchange between the adsorbed and the gas phase.
Date: April 23, 1999
Creator: Anderson, M.T.; Asink, R.A.; Kneller, J.M. & Pietrass, T.

222-S Analytical services final results for Tank 241-U-101, grab samples 1U-96-1 through 1U-96-4

Description: This document is the final, format IV, laboratory report for characterization of tank 241-U-101 (U-101) grab samples from risers 1 and 7. It transmits additional analytical data for specific gravity (Sp.G.), and all raw analytical data which were not provided in the 45-day report. The 45-day report is attached to this final report as Part II. Secondary analyses were not performed on any of the U-101 samples. This is because none of the primary analyte limits, which trigger the performance of secondary analyses, were exceeded. Grab samples were taken on May 29, 1996 and May 30, 1996 from risers 1 and 7, respectively, and were received at the 222-S Laboratory on the same days that they were collected. Analyses were performed in accordance with the Tank Sampling and Analysis Plan (TSAP) for this tank and the Safety Screening Data Quality Objective (DQO). The samples were analyzed for differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha activity (AT), visual appearance, bulk density, and specific gravity. A sample data summary table, includes sample analytical data accompanied by quality control data (for example, duplicate, spike, blank and standard results and detection limits and counting efforts). The table includes data for DSC, TGA, AT, bulk density, volume percent solids and Sp.G. analyses. Data regarding the visual appearance of samples, volume percent solids and density of the solids are provided in tabular form of the 45-day report (attached as Part II). The table of the 45-day report also associates the original customer sample number with corresponding laboratory sample numbers. The TSAP specified notification limits for only DSC and total alpha. Notification limits were not exceeded for DSC or total alpha analyses for any of the samples, consequently immediate notifications were not necessary and were not made.
Date: August 23, 1996
Creator: Miller, G. L.

242-A/LERF programmable Logic Controller Ladder. Revision 1

Description: This document defines and describes the user-generated application software written to transmit digital and analog signals from the Liquid Effluent Retention Facility (LERF) to the 242-A Evaporator Distributed Control System (DCS). PLCs and modems were installed in the 242-A Evaporator by Project W-105 (LERF) to transmit 6 analog liquid level signals, 6 range alarms based on the analog signals, and 6 leak detection and pump status signals to the 242-A Distributive Control System (DCS) from LERF. Communications between the two facilities are also monitored and alarm on the DCS. Following the Project W-105 completion, the communications and signal mix were modified by Project C-018H (ETF). The current PLC software (including ladder logic and data tables), PLC hardware settings, and modern option settings to transmit the signals and monitor communications are documented and described in this document.
Date: May 23, 1995
Creator: Teats, M.C.

A 1200 element detector system for synchrotron-based coronary angiography

Description: A 1200 channel Si(Li) detector system has been developed for transvenous coronary angiography experiments using synchrotron radiation. It is part of the synchrotron medical imaging facility at the National Synchrotron Light Source. The detector is made from a single crystal of lithium-drifted silicon with an active area 150 mm long {times} 11 mm high {times} 5 mm thick. The elements are arranged in two parallel rows of 600 elements with a center-to-center spacing of 0.25 mm. All 1200 elements are read out simultaneously every 4 ms. A Intel 80486 based computer with a high speed digital signal processing interface is used to control the beamline hardware and to acquire a series of images. The signal-to-noise, linearity and resolution of the system have been measured. Human images have been taken with this system.
Date: August 23, 1993
Creator: Thompson, A. C.; Lavender, W. M.; Rubenstein, E.; Giacomini, J. C.; Rosso, V.; Schulze, C. et al.

1999 Leak Detection and Monitoring and Mitigation Strategy Update

Description: This document is a complete revision of WHC-SD-WM-ES-378, Rev 1. This update includes recent developments in Leak Detection, Leak Monitoring, and Leak Mitigation technologies, as well as, recent developments in single-shell tank retrieval technologies. In addition, a single-shell tank retrieval release protection strategy is presented.
Date: September 23, 1999
Creator: OHL, P.C.

21st Century jobs initiative - Tennessee`s Resource Valley. Final report

Description: Tennessee`s Resource Valley, a regional economic development organization, was asked to facilitate a two-year, $750,000 grant from the Department of Energy. The grant`s purpose was to make the East Tennessee region less dependent on federal funds for its economic well-being and to increase regional awareness of the advantages of proximity to the Department of Energy facilities in Oak Ridge. The mission of Tennessee`s Resource Valley is to market the business location advantages of mid-East Tennessee to corporate decision makers and to facilitate regional initiatives that impact the creation of quality job opportunities. Tennessee`s Resource Valley represents fifteen (15) counties in East Tennessee: Anderson, Blount, Campbell, Claiborne, Cocke, Grainger, Jefferson, Knox, Loudon, Monroe, Morgan, Roane, Scott, Sevier and Union.
Date: December 23, 1996

29th Annual PolyMAC Meeting: book of abstracts

Description: A sixteen-run, Resolution IV, fractional factorial screening design has been used to evaluate the relative significance of seven independent material and process variables for an electrically deposited commercial acrylic paint. A Resolution IV design was chosen so that variable interactions could be detected without any interference from the effects of the variables themselves. Because resource limitations did not permit use of a Resolution V design, the two-way interactions were confounded with one another in groups of three, which unfortunately made interpretation of the results more complicated. Each design point was replicated once and a pair of centerpoints were run at the beginning, in the middle and at the end of the design points. A total of 38 test panels were prepared. Independent variables used in this experiment were total charge, current density, mixer speed, silica content, crossover point, temperature and solids fraction. The magnitude of each independent variable's effect on the dependent response variables was estimated by fitting a first-order model with two-way interaction terms. Three-way interactions were assumed to be insignificant. Interaction confounding was eliminated by using the significance of the independent variables to determine which of the three possible interactions was significant. Data analysis was performed using the Bayes Plot option of the JMP statistics program from SAS Institute. Only effects with a posterior probability equal to or greater than 0.95 were considered to be significant. Response variables analyzed were weight deposited, film thickness, surface roughness and plating efficiency. Results of the analysis are summarized. The following conclusions were formulated from the analysis of this experiment: Centerpoint behavior brings shelf-stability of the aqueous paint baths into question; Interactions among the material and process variables are present and significant; The magnitudes of some interaction effects equal or exceed the magnitudes of some of the effects of the independent variables; ...
Date: July 23, 1999
Creator: Balazs, B

2nd Generation PFBC Systems R&D Phase 2 AND Phase 3

Description: No work was performed; the two remaining Multi Annular Swirl Burner test campaigns are on hold pending selection of a new test facility (replacement for the shut down UTSI burner test facility) and identification of associated testing costs. The Second-Generation PFB Combustion Plant conceptual design prepared in 1987 is being updated to reflect the benefit of pilot plant test data and the latest advances in gas turbine technology. The updated plant is being designed to operate with 95 percent sulfur capture and a single Siemens Westinghouse (SW) 501G gas turbine. Using carbonizer and gas turbine data generated by Foster Wheeler (FW) and SW respectively, Parsons Energy and Chemicals Group prepared preliminary plant heat and materials based on carbonizer operating temperatures of 1700 and 1800 F and found the former to yield the higher plant efficiency. As a result, 1700EF has been selected as the preferred operating condition for the carbonizer. The previous first cut plant heat and material balance was refined and it predicts a 47.7% plant efficiency (HHV) with a net power output of 421 MWe. The latter includes a plant auxiliary load estimated to be 23.48 MWe or 5.26% of the gross plant power and a transformer loss of 1.52 MWe. Coal drying is through natural gas combustion, and the thermal energy input of the natural gas has also been included in the heat rate calculation. Figure 1 presents the plant preliminary full load heat and material balance. In this arrangement, evaporation and primary steam superheating tube surfaces are placed in both the pressurized circulating fluidized bed boiler (PCFB) and the gas turbine heat recovery steam generator (HRSG). The superheated steam from these units is mixed and then heated to 1050 F in the PCFB finishing superheater. With regard to steam reheating, the primary stage is located at ...
Date: December 23, 1999
Creator: Robertson, Archie

Accelerator modeling at SPEAR

Description: The response matrix, consisting of the closed orbit change at each beam position monitor (BPM) due to corrector magnet excitations, was measured and analyzed in order to calibrate a linear optics model of SPEAR. The model calibration was accomplished by varying model parameters to minimize the chi-square difference between the measured and the model response matrices. The singular value decomposition (SVD) matrix inversion method was used to solve the simultaneous equations. The calibrated model was then used to calculate corrections to the operational lattice. The results of the calibration and correction procedures are presented.
Date: May 23, 1997
Creator: LeBlanc, G. & Corbett, W.J.

Acceptable Knowledge Document for INEEL Stored Transuranic Waste -- Rocky Flats Plant Waste. Revision 2

Description: This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.
Date: January 23, 1998

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

Description: Since beginning operations in 1954, the Department of Energy's Savannah River Site FB-Line conducted atomic energy defense activities consistent with the listing in Section 10101(3) of the Nuclear Waste Policy Act of 1982. The facility mission was to process and convert dilute plutonium solution into highly purified weapons grade plutonium metal. As a result of various activities conducted in support of the mission (e.g., operation, maintenance, repair, clean up, and facility modifications), the facility generated transuranic waste. This document, along with referenced supporting documents, provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration,equipment, process operations, and waste management practices.
Date: August 23, 1999
Creator: Lunsford, G.F.

Acceptance test report for ENRAF control panel software

Description: On March 5, 1998, the ENRAF Control Panel Software program was acceptance tested per HNF-1991 Revision 0. The test was performed at the Department of Energy`s Hanford Site, 200 West Area, building MO-281. The test validated the functionality of the software for use by project W-320, C-1 06 Retrieval. The purpose of the test procedure was to partially verify the functionality of the ENRAF Control Panel Software. The test cycled through the majority of functions within the program. Functions not tested will be tested per Operational Test Procedure OTP-320-01 0 at a later date. The following criteria was used to determine whether the software passed or failed the test. The gauge responds correctly (as described in vendor documentation, Reference 1) to all commands sent through the program. If gauge related error codes are encountered, they may be cleared either through the PET or the program. However, the program, while running, must provide some indication of all gauge related errors encountered. If any of the pass criteria are not met and cannot be immediately resolved. If the system crashes for reasons that are clearly related to program performance and cannot be immediately resolved.
Date: March 23, 1998
Creator: Huber, J. H.

Acceptance test report for the AY-102 ENRAF densitometer

Description: On February 11, 1998, the AY-1 02, Riser 15E ENRAF Densitometer was acceptance tested per HNF-SD-WM-ATP-077. The test was performed at the Department of Energy`s Hanford Site, 200 East Area, building MO-407. The test validated the functionality of the Densitometer for use by project W-320, C-1 06 Retrieval. The purpose of the test procedure was to verify the functionality of the ENRAF Series 854 ATG densitometer. Typically, all ENRAF Series 854 ATGs are acceptance tested before transport to the field. The ATP, as performed for level gauges, sets default program values within the gauge and verifies the gauge`s force transducer calibration.
Date: March 23, 1998
Creator: Huber, J. H.

Accident Management & Risk-Based Compliance With 40 CFR 68 for Chemical Process Facilities

Description: A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision-makers may use the Accident Progression Event Tree approach to identify the best countermeasure for minimizing deleterious consequences to receptor groups before the atmospheric release has initiated. It is concluded that the chemical process industry may use this methodology as a supplemental information provider to better comply with the Environmental Protection Agency`s proposed 40 CFR 68 Risk Management Program rule. An illustration using a benzene-nitric acid potential interaction demonstrates the value of the logic process. The identification of worst-case releases and planning for emergency response are improved through these methods, at minimum. It also provides a systematic basis for prioritizing facility modifications to correct vulnerabilities.
Date: August 23, 1995
Creator: O`Kula, K.R.; Taylor, R.P. Jr. & Ashbaugh, S.G.