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Corrective Action Investigation Plan for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage, Nevada Test Site, Nevada, Revision 0. UPDATED WITH RECORD OF TECHNICAL CHANGE No.1 (open access)

Corrective Action Investigation Plan for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage, Nevada Test Site, Nevada, Revision 0. UPDATED WITH RECORD OF TECHNICAL CHANGE No.1

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. A CAU consists of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the CAU 321 Area 22 Weather Station Fuel Storage, CAS 22-99-05 Fuel Storage Area. For purposes of this discussion, this site will be referred to as either CAU 321 or the Fuel Storage Area. The Fuel Storage Area is located in Area 22 of the Nevada Test Site (NTS). The NTS is approximately 105 …
Date: February 8, 1999
Creator: /NV, U.S. DOE
System: The UNT Digital Library
Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada (open access)
Record of Technical Change No.1 for ``Fluid Management Plan for the Project Shoal Area Off-sites Project'' (open access)

Record of Technical Change No.1 for ``Fluid Management Plan for the Project Shoal Area Off-sites Project''

This Record of Technical Change provides updates to the technical information included in the ``Fluid Management Plan for the Project Shoal Area Off-sites Project,'' April 1999
Date: November 22, 1999
Creator: /NV, USDOE
System: The UNT Digital Library
Record of Technical Change No.2 for ``Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada'' (open access)

Record of Technical Change No.2 for ``Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada''

This Record of Technical Change provides updates to the technical information included in ``Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada.''
Date: November 19, 1999
Creator: /NV, USDOE
System: The UNT Digital Library
[Tennessee Health Studies Agreement] Releases of contaminants from Oak Ridge facilites and risks to public health (open access)

[Tennessee Health Studies Agreement] Releases of contaminants from Oak Ridge facilites and risks to public health

Tennessee Health Studies Agreement-Releases of Contaminants from Oak Ridge Facilities
Date: September 30, 1999
Creator: 741-0388, Patrick Lippford-Tennessee Department of Health (615)
System: The UNT Digital Library
Pre-conceptual Design of a Rapid Cycling Medical Synchrotron (open access)

Pre-conceptual Design of a Rapid Cycling Medical Synchrotron

N/A
Date: October 1, 1999
Creator: A., Favale; Myers, T.; Rathke, J.; Sredniawski, J.; Todd, A.; Barton, D. et al.
System: The UNT Digital Library
Can Data Recognize Its Parent Distribution? (open access)

Can Data Recognize Its Parent Distribution?

This study is concerned with model selection of lifetime and survival distributions arising in engineering reliability or in the medical sciences. We compare various distributions, including the gamma, Weibull and lognormal, with a new distribution called geometric extreme exponential. Except for the lognormal distribution, the other three distributions all have the exponential distribution as special cases. A Monte Carlo simulation was performed to determine sample sizes for which survival distributions can distinguish data generated by their own families. Two methods for decision are by maximum likelihood and by Kolmogorov distance. Neither method is uniformly best. The probability of correct selection with more than one alternative shows some surprising results when the choices are close to the exponential distribution.
Date: May 1, 1999
Creator: A.W.Marshall; J.C.Meza & Olkin, and I.
System: The UNT Digital Library
Test Plan for New SY Farm Annulus Leak Detectors (open access)

Test Plan for New SY Farm Annulus Leak Detectors

This document provides a plan for testing a new annulus leak detection device in the annulus of the waste storage tank 241 SY-102.
Date: August 13, 1999
Creator: ABUNDO, R.
System: The UNT Digital Library
Project Hanford management contract quality improvement project management plan (open access)

Project Hanford management contract quality improvement project management plan

On July 13, 1998, the U.S. Department of Energy, Richland Operations Office (DOE-RL) Manager transmitted a letter to Fluor Daniel Hanford, Inc. (FDH) describing several DOE-RL identified failed opportunities for FDH to improve the Quality Assurance (QA) Program and its implementation. In addition, DOE-RL identified specific Quality Program performance deficiencies. FDH was requested to establish a periodic reporting mechanism for the corrective action program. In a July 17, 1998 response to DOE-RL, FDH agreed with the DOE concerns and committed to perform a comprehensive review of the Project Hanford Management Contract (PHMC) QA Program during July and August, 1998. As a result, the Project Hanford Management Contract Quality Improvement Plan (QIP) (FDH-3508) was issued on October 21, 1998. The plan identified corrective actions based upon the results of an in-depth Quality Program Assessment. Immediately following the scheduled October 22, 1998, DOE Office of Enforcement and Investigation (EH-10) Enforcement Conference, FDH initiated efforts to effectively implement the QIP corrective actions. A Quality Improvement Project (QI Project) leadership team was assembled to prepare a Project Management Plan for this project. The management plan was specifically designed to engage a core team and the support of representatives from FDH and the major subcontractors …
Date: March 25, 1999
Creator: ADAMS, D.E.
System: The UNT Digital Library
B Plant Complex preclosure work plan (open access)

B Plant Complex preclosure work plan

This preclosure work plan describes the condition of the dangerous waste treatment storage, and/or disposal (TSD) unit after completion of the B Plant Complex decommissioning Transition Phase preclosure activities. This description includes waste characteristics, waste types, locations, and associated hazards. The goal to be met by the Transition Phase preclosure activities is to place the TSD unit into a safe and environmentally secure condition for the long-term Surveillance and Maintenance (S&M) Phase of the facility decommissioning process. This preclosure work plan has been prepared in accordance with Section 8.0 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1996). The preclosure work plan is one of three critical Transition Phase documents, the other two being: B Plant End Points Document (WHC-SD-WM-TPP-054) and B Plant S&M plan. These documents are prepared by the U.S. Department of Energy, Richland Operations Office (DOE-RL) and its contractors with the involvement of Washington State Department of Ecology (Ecology). The tanks and vessels addressed by this preclosure work plan are limited to those tanks end vessels included on the B Plant Complex Part A, Form 3, Permit Application (DOE/RL-88-21). The criteria for determining which tanks or vessels are in the Part …
Date: February 2, 1999
Creator: ADLER, J.G.
System: The UNT Digital Library
Periodic Boundary Conditions in the ALEGRA Finite Element Code (open access)

Periodic Boundary Conditions in the ALEGRA Finite Element Code

This document describes the implementation of periodic boundary conditions in the ALEGRA finite element code. ALEGRA is an arbitrary Lagrangian-Eulerian multi-physics code with both explicit and implicit numerical algorithms. The periodic boundary implementation requires a consistent set of boundary input sets which are used to describe virtual periodic regions. The implementation is noninvasive to the majority of the ALEGRA coding and is based on the distributed memory parallel framework in ALEGRA. The technique involves extending the ghost element concept for interprocessor boundary communications in ALEGRA to additionally support on- and off-processor periodic boundary communications. The user interface, algorithmic details and sample computations are given.
Date: November 1, 1999
Creator: AIDUN,JOHN B.; ROBINSON,ALLEN C. & WEATHERBY,JOE R.
System: The UNT Digital Library
Representative volume size: A comparison of statistical continuum mechanics and statistical physics (open access)

Representative volume size: A comparison of statistical continuum mechanics and statistical physics

In this combination background and position paper, the authors argue that careful work is needed to develop accurate methods for relating the results of fine-scale numerical simulations of material processes to meaningful values of macroscopic properties for use in constitutive models suitable for finite element solid mechanics simulations. To provide a definite context for this discussion, the problem is couched in terms of the lack of general objective criteria for identifying the size of the representative volume (RV) of a material. The objective of this report is to lay out at least the beginnings of an approach for applying results and methods from statistical physics to develop concepts and tools necessary for determining the RV size, as well as alternatives to RV volume-averaging for situations in which the RV is unmanageably large. The background necessary to understand the pertinent issues and statistical physics concepts is presented.
Date: May 1, 1999
Creator: AIDUN,JOHN B.; TRUCANO,TIMOTHY G.; LO,CHI S. & FYE,RICHARD M.
System: The UNT Digital Library
A Numerical Feasibility Study of Three-Component Induction Logging for Three Dimensional Imaging About a Single Borehole (open access)

A Numerical Feasibility Study of Three-Component Induction Logging for Three Dimensional Imaging About a Single Borehole

A theoretical analysis has been completed for a proposed induction logging tool designed to yield data which are used to generate three dimensional images of the region surrounding a well bore. The proposed tool consists of three mutually orthogonal magnetic dipole sources and multiple 3 component magnetic field receivers offset at different distances from the source. The initial study employs sensitivity functions which are derived by applying the Born Approximation to the integral equation that governs the magnetic fields generated by a magnetic dipole source located within an inhomogeneous medium. The analysis has shown that the standard coaxial configuration, where the magnetic moments of both the source and the receiver are aligned with the axis of the well bore, offers the greatest depth of sensitivity away from the borehole compared to any other source-receiver combination. In addition this configuration offers the best signal-to-noise characteristics. Due to the cylindrically symmetric nature of the tool sensitivity about the borehole, the data generated by this configuration can only be interpreted in terms of a two-dimensional cylindrical model. For a fill 3D interpretation the two radial components of the magnetic field that are orthogonal to each other must be measured. Coil configurations where both …
Date: August 1, 1999
Creator: ALUMBAUGH, DAVID L. & WILT, MICHAEL J.
System: The UNT Digital Library
Salinas - User's Notes (open access)

Salinas - User's Notes

Salinas provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of weapons systems. This document provides a users guide to the input for Salinas. Details of input specifications for the different solution types, output options, element types and parameters are included. The appendices contain detailed examples, and instructions for running the software on parallel platforms.
Date: November 1, 1999
Creator: ALVIN,KENNETH F.; BHARDWAJ,MANOJ K.; DRIESSEN,BRIAN; REESE,GARTH M. & SEGALMAN,DANIEL J.
System: The UNT Digital Library
DESIGN AND ANALYSIS OF THE SNS CCL HOT MODEL WATER COOLING SYSTEM USING THE SINDA/FLUINT NETWORK MODELING TOOL (open access)

DESIGN AND ANALYSIS OF THE SNS CCL HOT MODEL WATER COOLING SYSTEM USING THE SINDA/FLUINT NETWORK MODELING TOOL

This report presents results for design and analysis of the hot model water cooling system for the Spallation Neutron Source (SNS) coupled-cavity linac (CCL). The hot model, when completed, will include segments for both the CCL and coupled-cavity drift-tube linac (CCDTL). The scope of this report encompasses the modeling effort for the CCL portion of the hot model. This modeling effort employed the SINDA/FLUINT network modeling tool. This report begins with an introduction of the SNS hot model and network modeling using SINDA/FLUINT. Next, the development and operation of the SINDA/FLUINT model are discussed. Finally, the results of the SINDA/FLUINT modeling effort are presented and discussed.
Date: November 1, 1999
Creator: AMMERMAN, C. & BERNARDIN, J.
System: The UNT Digital Library
Corrosion of Uranium in Desert Soil, with Application to GCD Source Term M (open access)

Corrosion of Uranium in Desert Soil, with Application to GCD Source Term M

Uranium fragments from the Sandia Sled Track were studied as analogues for weapons components and depleted uranium buried at the Greater Confinement Disposal (GCD) site in Nevada. The Sled Track uranium fragments originated as weapons mockups and counterweights impacted on concrete and soil barriers, and experienced heating and fragmentation similar to processes thought to affect the Nuclear Weapons Accident Residues (NWAR) at GCD. Furthermore, the Sandia uranium was buried in unsaturated desert soils for 10 to 40 years, and has undergone weathering processes expected to affect the GCD wastes. Scanning electron microscopy, X-ray diffraction and microprobe analyses of the fragments show rapid alteration from metals to dominantly VI-valent oxy-hydroxides. Leaching studies of the samples give results consistent with published U-oxide dissolution rates, and suggest longer experimental periods (ca. 1 year) would be required to reach equilibrium solution concentrations. Thermochemical modeling with the EQ3/6 code indicates that the uranium concentrations in solutions saturated with becquerelite could increase as the pore waters evaporate, due to changes in carbonate equilibria and increased ionic strength.
Date: September 1, 1999
Creator: ANDERSON, HOWARD L.; BACA, JULIANNE; KRUMHANSL, JAMES L.; STOCKMAN, HARLAN W. & THOMPSON, MOLLIE E.
System: The UNT Digital Library
Plutonium reclamation facility (PRF), building 236-Z layup plan (open access)

Plutonium reclamation facility (PRF), building 236-Z layup plan

This document reviews each system inside PRF to determine the operation and maintenance requirements necessary to maintain safe and predictable system performance for facility systems needed to remain operational while minimizing the maintenance and surveillance being performed. Also covered are the actions required to place PRF in a safe layup configuration while minimizing hazards and taking into account the need for reactivation of certain equipment when cleanup work commences in the future.
Date: April 6, 1999
Creator: ANDERSON, R.N.
System: The UNT Digital Library
Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A (open access)

Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A

This report was prepared to evaluate the compliance of Cask Transportation Facility Modifications (CTFM) to DOE Order 6430.1A.
Date: July 14, 1999
Creator: ARD, K.E.
System: The UNT Digital Library
Roles and Delegation of Authority (R/DA) System (open access)

Roles and Delegation of Authority (R/DA) System

The processes of defining managerial roles and providing for delegation of authority are essential to any enterprise. At most large organizations, these processes are defined in policy manuals and through sets of standard operating procedures for many, if not all, business and administrative functions. Many of these staff-initiated, administrative functions require the routing of documents for approval to one or more levels of management. These employee-oriented, back office types of workflows tend to require more flexibility in determining to whom these documents should go to, while, at the same time, providing the responsible parties with the flexibility to delegate their approval authority or allow others to review their work. Although this practice is commonplace in manual, paper-based processes that exist in many organizations, it is difficult to provide the same flexibility in the more structured, electronic-based, workflow systems. The purpose of this report is to present a framework or architecture for creating a R/DA system and provide some insights associated with its design and utilization. To improve understanding and clarify subsequent discussion, the goals and requirements for the major R/DA system components, namely, the database and interface modules, are initially presented along with the identification of important concepts and the …
Date: November 1, 1999
Creator: Abbott, John P.; Hutchins, James C. & Schoch, David G.
System: The UNT Digital Library
Screening Level Risk Assessment for the New Waste Calcining Facility (open access)

Screening Level Risk Assessment for the New Waste Calcining Facility

This screening level risk assessment evaluates potential adverse human health and ecological impacts resulting from continued operations of the calciner at the New Waste Calcining Facility (NWCF) at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory (INEEL). The assessment was conducted in accordance with the Environmental Protection Agency (EPA) report, Guidance for Performing Screening Level Risk Analyses at Combustion Facilities Burning Hazardous Waste. This screening guidance is intended to give a conservative estimate of the potential risks to determine whether a more refined assessment is warranted. The NWCF uses a fluidized-bed combustor to solidify (calcine) liquid radioactive mixed waste from the INTEC Tank Farm facility. Calciner off volatilized metal species, trace organic compounds, and low-levels of radionuclides. Conservative stack emission rates were calculated based on maximum waste solution feed samples, conservative assumptions for off gas partitioning of metals and organics, stack gas sampling for mercury, and conservative measurements of contaminant removal (decontamination factors) in the off gas treatment system. Stack emissions were modeled using the ISC3 air dispersion model to predict maximum particulate and vapor air concentrations and ground deposition rates. Results demonstrate that NWCF emissions calculated from best-available process knowledge would result in …
Date: May 1, 1999
Creator: Abbott, M. L.; Keck, K. N.; Schindler, R. E.; VanHorn, R. L.; Hampton, N. L. & Heiser, M. B.
System: The UNT Digital Library
Air Dispersion Modeling of Mine Waste in the Southeast Missouri Old Lead Belt (open access)

Air Dispersion Modeling of Mine Waste in the Southeast Missouri Old Lead Belt

Past lead ore processing conducted in the Southeast Missouri Old Lead Belt since the 1700s has left numerous large areas of lead contamination in elevated piles of fine gravel waste called “chat” and dried-out tailings ponds. Wind suspension and atmospheric dispersion are known to transport these materials to the surrounding communities where the lead could pose a human health threat through inhalation or ingestion of the deposited contamination. The purpose of this study was to estimate potential wind suspension rates, perform dispersion modeling of the tailings and chat sources, and determine ground surface deposition rates and potential soil concentrations of lead in the surrounding areas. The results can be used to prioritize soil sampling locations, site air monitors, help identify the source of soil lead contamination, and to help develop remediation plans. Numerous, large complex sources in the region were parameterized into 33 area sources with the aid of digital aerial photos, digitized typographic maps, Geographic Information Systems (GIS) software, and site inspections. An AP-42 particulate emission model was used to estimate lower- and upper-bound hourly emission rates using six years of hourly wind speed data obtained from the St. Louis Airport. The emissions model accounted for wind speed, precipitation, …
Date: October 1, 1999
Creator: Abbott, Michael Lehman
System: The UNT Digital Library
Chamber and target technology development for inertial fusion energy (open access)

Chamber and target technology development for inertial fusion energy

Fusion chambers and high pulse-rate target systems for inertial fusion energy (IFE) must: regenerate chamber conditions suitable for target injection, laser propagation, and ignition at rates of 5 to 10 Hz; extract fusion energy at temperatures high enough for efficient conversion to electricity; breed tritium and fuel targets with minimum tritium inventory; manufacture targets at low cost; inject those targets with sufficient accuracy for high energy gain; assure adequate lifetime of the chamber and beam interface (final optics); minimize radioactive waste levels and annual volumes; and minimize radiation releases under normal operating and accident conditions. The primary goal of the US IFE program over the next four years (Phase I) is to develop the basis for a Proof-of-Performance-level driver and target chamber called the Integrated Research Experiment (IRE). The IRE will explore beam transport and focusing through prototypical chamber environment and will intercept surrogate targets at high pulse rep-rate. The IRE will not have enough driver energy to ignite targets, and it will be a non-nuclear facility. IRE options are being developed for both heavy ion and laser driven IFE. Fig. 1 shows that Phase I is prerequisite to an IRE, and the IRE plus NIF (Phase II) is prerequisite …
Date: April 7, 1999
Creator: Abdou, M.; Besenbruch, G.; Duke, J.; Forman, L.; Goodin, D.; Gulec, K. et al.
System: The UNT Digital Library
Direct Measurement of A{sub c} using Inclusive Charm Tagging at the SLD Detector (open access)

Direct Measurement of A{sub c} using Inclusive Charm Tagging at the SLD Detector

We report a new measurement of A{sub c} using data obtained by SLD in 1993-98. This measurement uses a vertex tag technique, where the selection of a c hemisphere is based on the reconstructed mass of the charm hadron decay vertex. The method uses the 3D vertexing capabilities of SLD's CCD vertex detector and the small and stable SLC beams to obtain a high c-event tagging efficiency and purity of 28% and 82%, respectively. Charged kaons identified by the CRID detector and the charge of the reconstructed vertex provide an efficient quark-antiquark tag, with the analyzing power calibrated from the data. We obtain a preliminary result of A{sub c} = 0.603 {+-} 0.028 {+-} 0.023.
Date: July 14, 1999
Creator: Abe, K
System: The UNT Digital Library
New Measurement of A{sub b} at the Z{sup 0} Resonance Using a Vertex Charge Technique (open access)

New Measurement of A{sub b} at the Z{sup 0} Resonance Using a Vertex Charge Technique

We present a new preliminary measurement of the parity-violation parameter A{sub b} using a self-calibrating vertex-charge technique. In the SLD experiment we observe hadronic decays of Z{sup 0} bosons produced in collisions between longitudinally polarized electrons and unpolarized positrons at the SLAC Linear Collider. A sample of b{bar b} events is selected using the topologically reconstructed mass of B hadrons. From our 1996-1998 data sample of approximately 400,000 hadronic Z{sup 0} decays, we obtain A{sub b} = 0.897 {+-} 0.027(stat){sub -0.034}{sup +0.036}(syst).
Date: July 20, 1999
Creator: Abe, K
System: The UNT Digital Library