Search Results

open access

2-D Finite Element Cable and Box IEMP Analysis

Description: A 2-D finite element code has been developed for the solution of arbitrary geometry cable SGEMP and box IEMP problems. The quasi- static electric field equations with radiation- induced charge deposition and radiation-induced conductivity y are numerically solved on a triangular mesh. Multiple regions of different dielectric materials and multiple conductors are permitted.
Date: December 17, 1998
Creator: Scivner, G.J. & Turner, C.D.
Partner: UNT Libraries Government Documents Department
open access

A 2-D Self-Consistent DSMC Model for Chemically Reacting Low Pressure Plasma Reactors

Description: This paper will focus on the methodology of using a 2D plasma Direct Simulation Monte Carlo technique to simulate the species transport in an inductively coupled, low pressure, chemically reacting plasma system. The pressure in these systems is typically less than 20 mtorr with plasma densities of approximately 10{sup 17} {number_sign}/m{sup 3} and an ionization level of only 0.1%. This low ionization level tightly couples the neutral, ion, and electron chemistries and interactions in a system where the flow is subsonic. We present our strategy and compare simulation results to experimental data for Cl{sub 2} in a Gaseous Electronics Conference (GEC) reference cell modified with an inductive coil.
Date: June 17, 1999
Creator: Bartel, Timothy J.; Economou, Demetre & Johannes, Justine E.
Partner: UNT Libraries Government Documents Department
open access

3-D Numerical Modeling of a Complex Salt Structure

Description: Reliably processing, imaging, and interpreting seismic data from areas with complicated structures, such as sub-salt, requires a thorough understanding of elastic as well as acoustic wave propagation. Elastic numerical modeling is an essential tool to develop that understanding. While 2-D elastic modeling is in common use, 3-D elastic modeling has been too computationally intensive to be used routinely. Recent advances in computing hardware, including commodity-based hardware, have substantially reduced computing costs. These advances are making 3-D elastic numerical modeling more feasible. A series of example 3-D elastic calculations were performed using a complicated structure, the SEG/EAGE salt structure. The synthetic traces show that the effects of shear wave propagation can be important for imaging and interpretation of images, and also for AVO and other applications that rely on trace amplitudes. Additional calculations are needed to better identify and understand the complex wave propagation effects produced in complicated structures, such as the SEG/EAGE salt structure.
Date: February 17, 2000
Creator: House, L.; Larsen, S. & Bednar, J. B.
Partner: UNT Libraries Government Documents Department
captions transcript

9-11 Commission Hearing #12, June 17, 2004, Part 1

Description: Recording of the twelfth public hearing held by the National Commission on Terrorist Attacks upon the United States on June 17, 2004 at the NTSB Conference Center in Washington, D.C. The two-day hearing focused on two distinct topics: the 9-11 Plot and the federal government's immediate response to the attacks on September 11, 2001. This section includes the staff statement entitled improvising a homeland defense in addition to the panel on military response on 9/11, with testimony from Richard Myers, Charles Joseph Leidig, and Ralph E. Eberhart.
Date: June 17, 2004
Duration: 3 hours 11 minutes 29 seconds
Creator: National Commission on Terrorist Attacks upon the United States
Partner: UNT Libraries Government Documents Department
captions transcript

9-11 Commission Hearing #12, June 17, 2004, Part 2

Description: Recording of the twelfth public hearing held by the National Commission on Terrorist Attacks upon the United States on June 17, 2004 at the NTSB Conference Center in Washington, D.C. The two-day hearing focused on two distinct topics: the 9-11 Plot and the federal government's immediate response to the attacks on September 11, 2001. This section concludes the hearing, and includes the panel on FAA response on 9/11, with testimony from Monte Belger, Jeff Griffith, John White, and Benedict Sliney.
Date: June 17, 2004
Duration: 1 hour 24 minutes 03 seconds
Creator: National Commission on Terrorist Attacks upon the United States
Partner: UNT Libraries Government Documents Department
open access

21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION

Description: The objective of this calculation is to evaluate the required minimum burnup as a function of initial pressurized water reactor (PWR) assembly enrichment that would permit loading of spent nuclear fuel into the 21 PWR waste package with absorber plates design as provided in Attachment IV. This calculation is an example of the application of the methodology presented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent U-235, and a burnup range of 0 through 45 GWd/MTU. Higher burnups were not necessary because 45 GWd/MTU was high enough for the loading curve determination. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing PWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials. This calculation is subject to the ''Quality Assurance Requirements and Description'' (QARD) (DOE 2004) because it concerns engineered barriers that are included in the ''Q-List'' (BSC 2004k, Appendix A) as items important to safety and waste isolation.
Date: December 17, 2004
Creator: Scaglione, J.M.
Partner: UNT Libraries Government Documents Department
open access

45-day safety screen results for tank 241-U-204, push mode, cores 81 and 82

Description: This is the 45-Day report for the fiscal year 1995 tank 241-U-204 (U-204) push-mode characterization effort. Included are a summary of analytical results and copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans. Core samples 81 and 82 from tank U-204, obtained by the push-mode core sampling method, were received by the 222-S Laboratories. Each core consisted of only one segment. Both core samples and the field blank were extruded, subsampled, and analyzed in accordance with Reference 1. Drainable liquids and the field blank were analyzed at the segment level for energetics by DSC, percent water by TGA, and total organic carbon (TOC) by furnace oxidation. In addition, the presence or absence of any separable, presumably organic, layer in drainable liquid samples was noted and none was observed. The solids were analyzed directly at the half segment level for energetics by DSC, percent water by TGA, and TOC by persulfate oxidation. Total alpha activity was determined on fusion digestions of the sludge subsamples. No immediate notifications were necessary on samples from cores 81 or 82.
Date: May 17, 1995
Creator: Bell, K.E.
Partner: UNT Libraries Government Documents Department
open access

60 kilograms high explosive containment with multi-diagnostic capability

Description: In anticipation of increasingly stringent environmental regulations, Lawrence Livermore National Laboratory (LLNL) proposes to construct a 60 kilogram (kg) firing chamber to provide blast-effects containment for most of its open-air, high explosives, firing operations. Even though these operations are within current environmental limits, containment of the blast effects and hazardous debris will further drastically reduce emissions to the environment and minimize the generated hazardous waste.
Date: September 17, 1998
Creator: Simmons, L. F.
Partner: UNT Libraries Government Documents Department

['77 Board of Regents Group Photo]

Description: Photograph of nine members of the North Texas State University Board of Regents standing together on the landing of a stairwell for a group photo. All are wearing suits and ties. Four are resting their hands on the railing and the others stand behind them. The wall behind them has windows that open up on the lawn outside the building.
Date: January 17, 1977
Partner: UNT Libraries Special Collections
open access

100 Areas: (For Technical Progress Letter No. 97), May 7--13

Description: Physics information for the D and F piles is presented. Thermal conductivity, reactivity, and irradiation levels are included. Concerning the cooling systems: process water control, pressure drip studies, purging studies, corrosion, and gun barrel clearance of expanded graphite are discussed. (GHH)
Date: May 17, 1946
Creator: Jordan, W. E.
Partner: UNT Libraries Government Documents Department
open access

190-H drawdown test

Description: A discrepancy of about 1000 gpm has existed between the full-flow recorded 190, 105 and ROL flows. While past operating practices have not used the 190 or ROL flow rates for official purposes, the disquieting, though not theoretically unexplicable, differences require some quantitative resolution. On November 24, 1962, a drawdown test of the 190-H storage tanks was performed to establish the accuracy of the various flowmeters. The drawdown test of the 190 storage tanks was run at the beginning of a scheduled reactor shutdown. With the full reactor flow supplied by the electric process pumps feeding from the storage tanks, the 183-H supply to the storage tanks was valved off. Additionally, non-process water usually taken from the storage tanks was valved off. The storage tank water levels were taken, then recorded as a function of time.
Date: January 17, 1963
Creator: Cremer, B. R. & Bokish, K. P.
Partner: UNT Libraries Government Documents Department
open access

241-AZ-101 pump removal trough analysis

Description: As part of the current Hanford mission of environmental cleanup, various long length equipment must be removed from highly radioactive waste tanks. The removal of equipment will utilize portions of the Equipment Removal System for Project W320 (ERS-W320), specifically the 50 ton hydraulic trailer system. Because the ERS-W320 system was designed to accommodate much heavier equipment it is adequate to support the dead weight of the trough, carriage and related equipment for 241AZ101 pump removal project. However, the ERS-W320 components when combined with the trough and its` related components must also be analyzed for overturning due to wind loads. Two troughs were designed, one for the 20 in. diameter carriage and one for the 36 in. diameter carriage. A proposed 52 in. trough was not designed and, therefore is not included in this document. In order to fit in the ERS-W320 strongback the troughs were design with the same widths. Structurally, the only difference between the two troughs is that more material was removed from the stiffener plates on the 36 in trough. The reduction in stiffener plate material reduces the allowable load. Therefore, only the 36 in. trough was analyzed.
Date: October 17, 1995
Creator: Coverdell, B.L.
Partner: UNT Libraries Government Documents Department
open access

242-A evaporator safety analysis report

Description: This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.
Date: May 17, 1999
Creator: CAMPBELL, T.A.
Partner: UNT Libraries Government Documents Department
open access

300 Area waste acid treatment system closure plan

Description: The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.
Date: May 17, 1999
Creator: LUKE, S.N.
Partner: UNT Libraries Government Documents Department
open access

303-K Storage Facility report on FY98 closure activities

Description: This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined that the 303-K Building cannot be clean closed without additional closure activities. An additional evaluation will be needed to determine the specific activities required to clean close the 303-K Storage Facility. The radiological contamination at the 303-K Storage Facility is not addressed by the closure strategy.
Date: July 17, 1998
Creator: Adler, J. G.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen