A 3-D hydrodynamic dispersion model for modeling tracer transport in Geothermal Reservoirs (open access)

A 3-D hydrodynamic dispersion model for modeling tracer transport in Geothermal Reservoirs

A 3-D hydrodynamic dispersion model for tracer transport is developed and implemented into the TOUGH2 EOS3 (T2R3D) module. The model formulation incorporates a full dispersion tensor, based on a 3-D velocity field with a 3-D, irregular grid in a heterogeneous geological system. Two different weighting schemes are proposed for spatial average of 3-D velocity fields and concentration gradients to evaluate the mass flux by dispersion and diffusion of a tracer or a radionuclide. This new module of the TOUGH2 code is designed to simulate processes of tracer/radionuclide transport using an irregular, 3-D integral finite difference grid in non-isothermal, three-dimensional, multiphase, porous/fractured subsurface systems. The numerical method for this transport module is based on the integral finite difference scheme, as in the TOUGH2 code. The major assumptions of the tracer transport module are: (a) a tracer or a radionuclide is present and transported only within the liquid phase, (b) transport mechanisms include molecular diffusion and hydrodynamic dispersion in the liquid phase in addition to advection, and (c) first order decay and linear adsorption on rock grains are taken into account. The tracer or radionuclide is introduced as an additional mass component into the standard TOUGH2 formulation, time is discretized fully implicitly, …
Date: January 26, 1998
Creator: Wu, Yu-Shu & Pruess, Karsten
Object Type: Article
System: The UNT Digital Library
105-K Basin material design basis feed description for spent nuclear fuel project facilities (open access)

105-K Basin material design basis feed description for spent nuclear fuel project facilities

Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.
Date: January 8, 1998
Creator: Praga, A. N.
Object Type: Report
System: The UNT Digital Library
200 Area effluent treatment facility process control plan 98-02 (open access)

200 Area effluent treatment facility process control plan 98-02

This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP).
Date: January 30, 1998
Creator: Le, Elvis Q.
Object Type: Report
System: The UNT Digital Library
1996-1997 TEMA/DOE oversite annual report (open access)

1996-1997 TEMA/DOE oversite annual report

The Tennessee Emergency Management Agency (TEMA) has entered into a five-year agreement with the Department of Energy (DOE) to provide emergency response activities associated with the Oak Ridge Reservation (ORR). The Agreement in Principle (AIP) delineates the duties and responsibilities of the parties. The agreement tasked TEMA with the following responsibilities: develop offsite emergency plans; conduct emergency management training; develop offsite emergency organizations; develop emergency communications; develop emergency facilities; conduct exercises and drills; provide detection and protection equipment; and develop an emergency staff. This document reports on progress on these tasks during the past year.
Date: January 1, 1998
Creator: unknown
Object Type: Report
System: The UNT Digital Library
1996 Milestone Report 3GQH671M Synthesis of Ground-Water Discharge Deposits Near Yucca Mountain (open access)

1996 Milestone Report 3GQH671M Synthesis of Ground-Water Discharge Deposits Near Yucca Mountain

None
Date: January 1, 1998
Creator: Paces, J. B.; Whelan, J. F.; Mahan, S. A.; Bradbury, J. P.; Quade, J. & Neymark, L. A.
Object Type: Report
System: The UNT Digital Library
AA Fest. General Circulation Model Development: Past, Present and Future. A Symposium in Honor of Professor Akio Arakawa (open access)

AA Fest. General Circulation Model Development: Past, Present and Future. A Symposium in Honor of Professor Akio Arakawa

OAK-B135 AA Fest. General Circulation Model Development: Past, Present and Future. A Symposium in Honor of Professor Akio Arakawa
Date: January 20, 1998
Creator: Ide, K. & Wakimoto, R. M.
Object Type: Report
System: The UNT Digital Library
AA Fest General Circulation Model Development: Past, Present and Future. A Symposium in Honor of Professor Akio Arakawa (open access)

AA Fest General Circulation Model Development: Past, Present and Future. A Symposium in Honor of Professor Akio Arakawa

On January 20-22, 1998, ''AA Fest. A Symposium on General Circulation Model Development: Past, Present, and Future'' was held at the North West Campus Auditorium of University of California, Los Angeles, in honor of Professor Ako Arawaka. The symposium consisted of two-and-a-half-day technical presentations, along with a banquet in the opening evening and a reception during the poster session of the second evening.
Date: January 22, 1998
Creator: Ide, Kayo
Object Type: Article
System: The UNT Digital Library
Accelerator development for a radioactive beam facility based on ATLAS. (open access)

Accelerator development for a radioactive beam facility based on ATLAS.

The existing superconducting linac ATLAS is in many respects an ideal secondary beam accelerator for an ISOL (Isotope separator on-line) type radioactive beam facility. Such a facility would require the addition of two major accelerator elements: a low charge state injector for the existing heavy ion linac, and a primary beam accelerator providing 220 MV of acceleration for protons and light ions. Development work for both of these elements, including the option of superconducting cavities for the primary beam accelerator is discussed.
Date: January 8, 1998
Creator: Shepard, K. W.
Object Type: Article
System: The UNT Digital Library
Acceptable Knowledge Document for INEEL Stored Transuranic Waste -- Rocky Flats Plant Waste. Revision 2 (open access)

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

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, …
Date: January 23, 1998
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Acceptance inspection plan 105KE Facility modifications for fuel retrieval subproject (open access)

Acceptance inspection plan 105KE Facility modifications for fuel retrieval subproject

The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified, to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with …
Date: January 9, 1998
Creator: Shen, E.J.
Object Type: Report
System: The UNT Digital Library
Acceptance inspection plan 105KW Facility modifications for fuel retrieval subproject (open access)

Acceptance inspection plan 105KW Facility modifications for fuel retrieval subproject

The acceptance inspection of construction by Fluor Daniel Hanford (FDH) is performed to provide assurance that fabrication, construction, and installation are in accordance with approved contract documents. Approved contract documents used to perform inspections may include specifications, drawings, and contractor submittals such as fabrication drawings, procedures, etc. The amount or degree of inspection activity is tailored to the project as determined by the project team so that the effort and cost expended are commensurate with the importance of the facility in terms of function and safety. Inspections are documented to provide verification of the acceptability of the work performed. This document identifies the inspections and documentation forms to be provided. It is prepared and implemented with the understanding that the construction contractor is fully responsible for compliance with contract documents and for the quality of.work performed. Inspections performed are in accordance with approved procedures. The Manager of Acceptance Inspection is responsible for the implementation of this plan and assignment of personnel for the work. Inspections are conducted by personnel who are qualified and certified to perform their assigned task. The Acceptance Inspection Plan is organized in the Construction Specification Institute (CSI) format to cross reference design specification sections with sections …
Date: January 9, 1998
Creator: Shen, E.J.
Object Type: Report
System: The UNT Digital Library
Acid Pit Stabilization Project (Volume 1 - Cold Testing) and (Volume 2 - Hot Testing) (open access)

Acid Pit Stabilization Project (Volume 1 - Cold Testing) and (Volume 2 - Hot Testing)

During the summer and fall of Fiscal Year 1997, a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Treatability Study was performed at the Idaho National Engineering and Environmental Laboratory. The study involved subsurface stabilization of a mixed waste contaminated soil site called the Acid Pit. This study represents the culmination of a successful technology development effort that spanned Fiscal Years 1994-1996. Research and development of the in situ grout stabilization technique was conducted. Hardware and implementation techniques are currently documented in a patent pending with the United States Patent and Trademark Office. The stabilization technique involved using jet grouting of an innovative grouting material to form a monolith out of the contamination zone. The monolith simultaneously provides a barrier to further contaminant migration and closes voids in the soil structure against further subsidence. This is accomplished by chemical incorporation of contaminants into less soluble species and achieving a general reduction in hydraulic conductivity within the monolith. The grout used for this study was TECT-HG, a relatively dense iron oxide-based cementitious grout. The treatability study involved cold testing followed by in situ stabilization of the Acid Pit. Volume 1 of this report discusses cold testing, performed as part of a …
Date: January 1, 1998
Creator: Loomis, Guy G.; Zdinak, Andrew P.; Ewanic, Mark A. & Jessmore, James J.
Object Type: Report
System: The UNT Digital Library
Activation of materials proposed for use in superconducting linac applications (open access)

Activation of materials proposed for use in superconducting linac applications

Samples of construction materials proposed for use in both superconducting and conventional high-power linear accelerators have been activated with 800 and 2,000 MeV protons to study the decay characteristics of these activated materials. Irradiation times ranged from 10 minutes to 18.67 hours. The decay characteristics of these activated materials were measured and compared to calculated decay curves based on simplified assumptions.
Date: January 1, 1998
Creator: Hanson, A. L.; Snead, C. L.; Greene, G. A.; Chan, K. C. D. & Safa, H.
Object Type: Report
System: The UNT Digital Library
Adaptation of the fuzzy k-nearest neighbor classifier for manufacturing automation (open access)

Adaptation of the fuzzy k-nearest neighbor classifier for manufacturing automation

The use of supervised pattern recognition technologies for automation in the manufacturing environment require the development of systems that are easy to train and use. In general, these systems attempt to emulate an inspection or measurement function typically performed by a manufacturing engineer or technician. This paper describes a self-optimizing classification system for automatic decision making in the manufacturing environment. This classification system identifies and labels unique distributions of product defects denoted as signatures. The technique relies on encapsulating human experience through a teaching method to emulate the human response to various manufacturing situations. This has been successfully accomplished through the adaptation and extension of a feature-based, fuzzy k-nearest neighbor (k-NN) classifier that has been implemented in a pair-wise fashion. The classifier works with pair-wise combinations of the user-defined classes so that a significant reduction in feature space and problem complexity can be achieved. This k-NN implementation makes extensive use of hold-one-out results and fuzzy ambiguity information to optimize its performance. A semiconductor manufacturing case study will be presented. The technique uses data collected from in-line optical inspection tools to interpret and rapidly identify characteristic signatures that are uniquely associated with the manufacturing process. The system then alerts engineers to …
Date: January 1998
Creator: Tobin, K. W.; Gleason, S. S. & Karnowski, T. P.
Object Type: Article
System: The UNT Digital Library
Advanced 3D electromagnetic and particle-in-cell modeling on structured/unstructured hybrid grids (open access)

Advanced 3D electromagnetic and particle-in-cell modeling on structured/unstructured hybrid grids

New techniques have been recently developed that allow unstructured, free meshes to be embedded into standard 3-dimensional, rectilinear, finite-difference time-domain grids. The resulting hybrid-grid modeling capability allows the higher resolution and fidelity of modeling afforded by free meshes to be combined with the simplicity and efficiency of rectilinear techniques. Integration of these new methods into the full-featured, general-purpose QUICKSILVER electromagnetic, Particle-In-Cell (PIC) code provides new modeling capability for a wide variety of electromagnetic and plasma physics problems. To completely exploit the integration of this technology into QUICKSILVER for applications requiring the self-consistent treatment of charged particles, this project has extended existing PIC methods for operation on these hybrid unstructured/rectilinear meshes. Several technical issues had to be addressed in order to accomplish this goal, including the location of particles on the unstructured mesh, adequate conservation of charge, and the proper handling of particles in the transition region between structured and unstructured portions of the hybrid grid.
Date: January 1, 1998
Creator: Seidel, D. B.; Pasik, M. F.; Kiefer, M. L.; Riley, D. J. & Turner, C. D.
Object Type: Report
System: The UNT Digital Library
An advanced deterministic method for spent fuel criticality safety analysis (open access)

An advanced deterministic method for spent fuel criticality safety analysis

Over the past two decades, criticality safety analysts have come to rely to a large extent on Monte Carlo methods for criticality calculations. Monte Carlo has become popular because of its capability to model complex, non-orthogonal configurations or fissile materials, typical of real world problems. Over the last few years, however, interest in determinist transport methods has been revived, due shortcomings in the stochastic nature of Monte Carlo approaches for certain types of analyses. Specifically, deterministic methods are superior to stochastic methods for calculations requiring accurate neutron density distributions or differential fluxes. Although Monte Carlo methods are well suited for eigenvalue calculations, they lack the localized detail necessary to assess uncertainties and sensitivities important in determining a range of applicability. Monte Carlo methods are also inefficient as a transport solution for multiple pin depletion methods. Discrete ordinates methods have long been recognized as one of the most rigorous and accurate approximations used to solve the transport equation. However, until recently, geometric constraints in finite differencing schemes have made discrete ordinates methods impractical for non-orthogonal configurations such as reactor fuel assemblies. The development of an extended step characteristic (ESC) technique removes the grid structure limitations of traditional discrete ordinates methods. The …
Date: January 1, 1998
Creator: DeHart, M.D.
Object Type: Article
System: The UNT Digital Library
Advanced Oil Recovery Technologies for Improved Recovery From Slope Clastic Reservoirs, Nash Draw Brushy Canyon Pool, Eddy County, New Mexico (open access)

Advanced Oil Recovery Technologies for Improved Recovery From Slope Clastic Reservoirs, Nash Draw Brushy Canyon Pool, Eddy County, New Mexico

The overall goal of this project is to demonstrate that an advanced development drilling and pressure maintenance program based on advanced reservoir management methods can significantly improve oil recovery. The plan included developing a control area using standard reservoir management techniques and comparing its performance to an area developed using advanced methods. A key goal is to transfer advanced methodologies to oil and gas producers in the Permian Basin and elsewhere, and throughout the US oil and gas industry.
Date: January 30, 1998
Creator: Murphy, Mark B.
Object Type: Report
System: The UNT Digital Library
Advanced Thermally Stable Jet Fuels (open access)

Advanced Thermally Stable Jet Fuels

The Penn State program in advanced thermally stable jet fuels has five components: 1) development of mechanisms of degradation and solids formation; 2) quantitative measurement of growth of sub-micrometer and micrometer-sized particles during thermal stressing; 3) characterization of carbonaceous deposits by various instrumental and microscopic methods; 4) elucidation of the role of additives in retarding the formation of carbonaceous solids; and 5) assessment of the potential of producing high yields of cycloalkanes and hydroaromatics from coal.
Date: January 1, 1998
Creator: Boehman, A.; Song, C.; Schobert, H. H.; Coleman, M. M.; Hatcher, P. G. & Eser, S.
Object Type: Report
System: The UNT Digital Library
Aging and loss-of-coolant accident (LOCA) testing of electrical connections (open access)

Aging and loss-of-coolant accident (LOCA) testing of electrical connections

This report presents the results of an experimental program to determine the aging and loss-of-coolant accident (LOCA) behavior of electrical connections in order to obtain an initial scoping of their performance. Ten types of connections commonly used in nuclear power plants were tested. These included 3 types of conduit seals, 2 types of cable-to-device connectors, 3 types of cable-to-cable connectors, and 2 types of in-line splices. The connections were aged for 6 months under simultaneous thermal (99 C) and radiation (46 Gy/hr) conditions. A simulated LOCA consisting of sequential high dose-rate irradiation (3 kGy/hr) and high-temperature steam exposures followed the aging. Connection functionality was monitored using insulation resistance measurements during the aging and LOCA exposures. Because only 5 of the 10 connection types passed a post-LOCA, submerged dielectric withstand test, further detailed investigation of electrical connections and the effects of cable jacket integrity on the cable-connection system is warranted.
Date: January 1998
Creator: Nelson, C. F.
Object Type: Report
System: The UNT Digital Library
Aging of steel containments and liners in nuclear power plants (open access)

Aging of steel containments and liners in nuclear power plants

Aging of the containment pressure boundary in light water reactor plants is being addressed to understand the significant factors relating occurrence of corrosion efficacy of inspection and structural capacity reduction of steel containments and liners of concrete containments. and to make recommendations on use of risk models in regulatory decisions. Current regulatory in-service inspection requirements are reviewed and a summary of containment related degradation experience is presented. Current and emerging nondestructive examination techniques and a degradation assessment methodology for characterizing and quantifying the amount of damage present are described. Quantitative tools for condition assessment of aging structures using time dependent structural reliability analysis methods are summarized. Such methods provide a framework for addressing the uncertainties attendant to aging in the decision process. Results of this research provide a means for establishing current and estimating future structural capacity margins of containments, and to address the significance of incidences of reported containment degradation.
Date: January 1, 1998
Creator: Naus, D. J.; Oland, C. B.; Ellingwood, B. & Norris, W. E.
Object Type: Article
System: The UNT Digital Library
ALTERNATIVE FUELS AND CHEMICALS FROM SYNTHESIS GAS (open access)

ALTERNATIVE FUELS AND CHEMICALS FROM SYNTHESIS GAS

The overall objectives of this program are to investigate potential technologies for the conversion of synthesis gas to oxygenated and hydrocarbon fuels and industrial chemicals, and to demonstrate the most promising technologies at DOE's LaPorte, Texas, Slurry Phase Alternative Fuels Development Unit (AFDU). The program will involve a continuation of the work performed under the Alternative Fuels from Coal-Derived Synthesis Gas Program and will draw upon information and technologies generated in parallel current and future DOE-funded contracts.
Date: January 1, 1998
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Analysis of a micro-scale pump which uses controlled acoustic streaming for fluid locomotion (open access)

Analysis of a micro-scale pump which uses controlled acoustic streaming for fluid locomotion

In this report the analysis of a micro-scale pump is described. This micro-pump uses active control to produce a distributed body force in a fluid micro-channel. The desired effect of this body force is to drive fluid through the channel. Limitations, assumptions, and design parameters are discussed. The mathematical analysis of pump dynamics is explained in detail. A perturbation analysis is used on the equations of mass, momentum and state to produce equations of motion for first and second order effects. The first order effects are described by linear wave motion in the fluid and are found by using integral equation methods. The second order effects are driven by body forces resulting from first order effects. Thus, by controlling the production of wave motion in the channel, second order excitation can also be controlled. This report is all theory and therefore needs experimental validation. Although many of the assumptions used in this report have been used elsewhere in the literature and have been found to be sufficient, there are many aspects of the problem which have been left unresolved. In particular, flow separation in the fluid channel is a critical problem. If the fluid does not separate, pumping will occur …
Date: January 1, 1998
Creator: Dohner, J. L.
Object Type: Report
System: The UNT Digital Library
Analysis of gallium arsenide deposition in a horizontal chemical vapor deposition reactor using massively parallel computations (open access)

Analysis of gallium arsenide deposition in a horizontal chemical vapor deposition reactor using massively parallel computations

A numerical analysis of the deposition of gallium from trimethylgallium (TMG) and arsine in a horizontal CVD reactor with tilted susceptor and a three inch diameter rotating substrate is performed. The three-dimensional model includes complete coupling between fluid mechanics, heat transfer, and species transport, and is solved using an unstructured finite element discretization on a massively parallel computer. The effects of three operating parameters (the disk rotation rate, inlet TMG fraction, and inlet velocity) and two design parameters (the tilt angle of the reactor base and the reactor width) on the growth rate and uniformity are presented. The nonlinear dependence of the growth rate uniformity on the key operating parameters is discussed in detail. Efficient and robust algorithms for massively parallel reacting flow simulations, as incorporated into our analysis code MPSalsa, make detailed analysis of this complicated system feasible.
Date: January 1, 1998
Creator: Salinger, Andrew G.; Shadid, John N. & Hutchinson, S. A.
Object Type: Report
System: The UNT Digital Library
Analysis of hypervelocity impact test data (open access)

Analysis of hypervelocity impact test data

Experiments conducted by the Department of Defense provide an adequate basis for the determination of the fragment distribution and number from hypervelocity collisions. Models trained on only a portion of the data are shown to bias samples too far from the population to be useful for averaging over debris distributions or estimating fragment production rates. The average fragment production exponent is more appropriate for those purposes.
Date: January 1, 1998
Creator: Canavan, G. H.
Object Type: Report
System: The UNT Digital Library