1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation (open access)

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation

Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convective layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.
Date: January 1, 1993
Creator: Fort, J. A.; Bamberger, J. A.; Bates, J. M.; Enderlin, C. W. & Elmore, M. R.
Object Type: Report
System: The UNT Digital Library
1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation. Final report (open access)

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation. Final report

Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surface of the supernatant liquid. The supernatant is more commonly referred to as the convective layer and the slurry as the non-convective layer. Accumulation of gas (partly hydrogen) in the non-convective layer is suspected to be the key mechanism behind the gas burp phenomena, and several mitigation schemes are being developed to encourage a more uniform gas release rate (Benegas 1992). To support the full-scale hydraulic mitigation test, scaled experiments were performed to satisfy two objectives: 1. provide an experimental database for numerical- model validation; 2. establish operating parameter values required to mobilize the settled solids and maintain the solids in suspension.
Date: January 1993
Creator: Fort, J. A.; Bamberger, J. A.; Bates, J. M.; Enderlin, C. W. & Elmore, M. R.
Object Type: Report
System: The UNT Digital Library
Ab initio molecular orbital calculations of molten salt vapor complexes using Gaussian-2 theory: LiAlF[sub 4] and NaAlF[sub 4] (open access)

Ab initio molecular orbital calculations of molten salt vapor complexes using Gaussian-2 theory: LiAlF[sub 4] and NaAlF[sub 4]

The structures and energies of the molten salt vapor complexes LiAlF[sub 4] and NaAlF[sub 4] are studied using new high level ab initio molecular orbital methods. The structures are determined using Moller-Plesset perturbation theory to second-order and the total energies are determined using a recently introduced modification of Gaussian-2 (G2) theory. The total energies are used to determine relative energies of the corner-, edge-, and face-bridged structures and accurate reaction energies. The results are compared to previous theoretical and experimental studies.
Date: January 1, 1993
Creator: Curtiss, L.A.
Object Type: Article
System: The UNT Digital Library
Abort interlock diagnostic for protection of APS vacuum chamber (open access)

Abort interlock diagnostic for protection of APS vacuum chamber

The Advanced Photon Source (APS) vacuum system has been designed to be passively safe from bending magnet radiation heating at positron beam currents up to 30 mA. Above this value, certain components may be damaged from vertical beam missteering, although work is proceeding to raise the safe current threshold. Because of this, a system for preventing the misalignment of high power density beams is required. This report details a system for protection from dipole radiation only. Work on a system for ID radiation is continuing.
Date: January 1, 1993
Creator: Decker, G.
Object Type: Article
System: The UNT Digital Library
Abstracts of papers thirty-fourth ORNL/DOE conference on analytical chemistry in energy technology (open access)

Abstracts of papers thirty-fourth ORNL/DOE conference on analytical chemistry in energy technology

Less than 100 abstracts are included.
Date: 1993
Creator: unknown
Object Type: Article
System: The UNT Digital Library
Accelerator and Beam Transport Design Information (open access)

Accelerator and Beam Transport Design Information

This report contains viewgraphs on accelerator design and physics.
Date: January 1, 1993
Creator: Lawrence, George
Object Type: Article
System: The UNT Digital Library
Accelerator Research Studies (open access)

Accelerator Research Studies

The Accelerator Research Studies program at the University of Maryland, sponsored by the Department of Energy under grant number DE-FG05-91ER40642, is currently in the second year of a three-year funding cycle. The program consists of the following three tasks: TASK A, Study of Transport and Longitudinal Compression of Intense, High-Brightness Beams,'' (P.I., M. Reiser); TASK B, Study of Collective Ion Acceleration by Intense Electron Beams and Pseudospark Produced High Brightness Electron Beams,'' (Co-P.I.'s, W.W. Destler, M. Reiser, M.J. Rhee, and C.D. Striffler); TASK C, Study of a Gyroklystron High-Power Microwave Source for Linear Colliders,'' (Co-P.I.'s, V.L. Granatstein, W. Lawson, M. Reiser, and C.D. Striffler). In this report we document the progress that has been made during the past year for each of the three tasks.
Date: January 1, 1993
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Acceptance criteria for corroded carbon steel piping containing weld defects (open access)

Acceptance criteria for corroded carbon steel piping containing weld defects

Acceptance criteria for corroded low temperature, low pressure carbon steel piping containing weld defects is presented along with a typical application of these criteria. They are intended to preclude gross rupture or rapidly propagating failure due to uniform wall thinning, local wall thinning, pitting corrosion and weld defects. The minimum allowable uniform wail thickness is based on the code-of-record allowable stress and fracture criteria. Weld defects are postulated as potential sites for fracture initiation. CEGB/R6 failure assessment diagram is used as the fracture criteria to determine the minimum allowable wall thickness. Design of a large portion of the low temperature, low pressure piping is dominated by axial stresses. Existing local wall thinning acceptance criteria address high pressure piping where hoop stress dominates the design. The existing criteria is over conservative, in some cases, when used on low pressure piping. Local wall thinning criteria is developed to limit the axial stress on the locally thinned section, based on a reduced average thickness. Limits on pit density are also developed to provide acceptance criteria for pitted piping.
Date: January 1, 1993
Creator: Mertz, G. E.; Lam, P. S. & Awadalla, N. G.
Object Type: Article
System: The UNT Digital Library
Accessing Integrated Genomic Data Using GenoBase: A Tutorial, Part 1 (open access)

Accessing Integrated Genomic Data Using GenoBase: A Tutorial, Part 1

GenoBase integrates genomic information from many existing databases, offering convenient access to the curated data. This document is the first part of a two-part tutorial on how to use GenoBase for accessing integrated genomic data.
Date: January 1, 1993
Creator: Overbeek, R. & Price, M.
Object Type: Report
System: The UNT Digital Library
Accessing Integrated Genomic Data Using Genobase: A Tutorial, Part 1 (open access)

Accessing Integrated Genomic Data Using Genobase: A Tutorial, Part 1

GenoBase integrates genomic information from many existing databases, offering convenient access to the curated data. This document is the first part of a two-part tutorial on how to use GenoBase for accessing integrated genomic data.
Date: January 1, 1993
Creator: Overbeek, R. & Price, M.
Object Type: Report
System: The UNT Digital Library
ACHRO: A program to help design achromatic bends (open access)

ACHRO: A program to help design achromatic bends

ACHRO is a very simple 2000-line. FORTRAN code that provides help for the designer of the achromatic bend. Given a beam momentum, the program calculates the required drift lengths and dipole parameters which it will apply to any one of several different types of achromats. The types of achromats that the code helps to design include the Enge dual-270,'' the Brown 2-dipole, the Leboutet 3-dipole, and the Enge 4-dipole, as well as the periodic systems which can be designed to any order in symmetric, nonsymmetric and stair-step varieties. Given the dimensions into which a bend must fit, ACHRO will calculate the geometrical parameters in an X-Y plane for a single or multiple achromat, and for achromatic S-bend'' configurations where possible. ACHRO makes it very easy to optimize a bend with respect to drift lengths and magnet parameters by allowing the user to change parameter values and see the resulting calculation. Used in conjunction with a beam-transport code, ACHRO makes it possible for a designer to consider various types of achromatic bends in the same beamline layout in order to compare important bend characteristics such as dispersion, Isochronicity, sensitivity, geometric and chromatic aberrations, aperture requirements, space for diagnostics, etc., all of …
Date: January 1, 1993
Creator: Rusthoi, D.
Object Type: Article
System: The UNT Digital Library
Active Sites Environmental Monitoring Program FY 1995 Annual Report (open access)

Active Sites Environmental Monitoring Program FY 1995 Annual Report

Chapter 3 of US Department of Energy (DOE) Order 5820.2A (DOE 1988) specifies requirements for the management of facilities that were used for the disposal of radioactive solid low-level waste (LLW) on or after the date of the order. Activities in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) are governed by Chapter 3. Chapter 2 of 5820.2A covers the transuranic (TRU) waste storage areas in SWSA 5 North at ORNL. Both chapters require environmental monitoring to provide early warning of leaks before such leaks pose a threat to human health or the environment. Chapter 3 also requires the monitoring of LLW disposal facilities so that their performance can be evaluated. In order to comply with this Order, the Environmental Sciences Division (ESD) at ORNL implements the Active Sites Environmental Monitoring Program (ASEMP) for the Radioactive Solid Waste Operations Group (RSWOG) within the Waste Management and Remedial Action Division (WMRAD) at ORNL. The scope of ASEMP includes all ORNL waste disposal sites that were active on or after the date of the Order and that are under the operational control of RSWOG of WMRAD. This report continues a series of annual and semiannual reports that present …
Date: January 1, 1993
Creator: Morrisey, C.M.
Object Type: Report
System: The UNT Digital Library
Adaptive Transfer Function Networks (open access)

Adaptive Transfer Function Networks

Real-time pattern classification and time-series forecasting applications continue to drive artificial neural network (ANN) technology. As ANNs increase in complexity, the throughput of digital computer simulations decreases. A novel ANN, the Adaptive Transfer Function Network (ATF-Net), directly addresses the issue of throughput. ATF-Nets are global mapping equations generated by the superposition of ensembles of neurodes having arbitrary continuous functions receiving encoded input data. ATF-Nets may be implemented on parallel digital computers. An example is presented which illustrates a four-fold increase in computational throughput.
Date: January 1, 1993
Creator: Goulding, J.R. (Los Alamos National Lab., NM (United States) Portland State Univ., OR (United States). Dept. of Electrical Engineering)
Object Type: Article
System: The UNT Digital Library
An adaptive weighted diamond differencing method for three-dimensional, XYZ geometry (open access)

An adaptive weighted diamond differencing method for three-dimensional, XYZ geometry

About sixteen years ago, Bengt Carlson introduced a method for discretizing the neutral particle transport equation to achieve a positive solution while at the same time retaining much of the accuracy of the diamond differencing method. About six years later Russian researchers applied this work to their problems and extended it somewhat to enhance the flexibility of the method to incorporate monotonic properties of the solution. This latter work came to the attention of US researchers in late 1991 where it verified much of Carlson's conclusions in theory and in test problems. This method, called the adaptive weighted diamond (AWDD) method, is based upon a weighted diamond discretization of the transport equation with the weights chosen from a diamond difference prediction of the solution so as to correct it for positively and monotonicity. This work re-examines the method and extends it to three-dimensional XYZ geometry and demonstrates its potential for solving such problems accurately while achieving a much smoother solution than diamond with set-to-zero fixup and is as effective as the theta-weighted fixup method 3 while theoretically and operationally more satisfying.
Date: January 1, 1993
Creator: Alcouffe, R.E.
Object Type: Article
System: The UNT Digital Library
Addressing the insider threat (open access)

Addressing the insider threat

Computers have come to play a major role in the processing of information vital to our national security. As we grow more dependent on computers, we also become more vulnerable to their misuse. Misuse may be accidental, or may occur deliberately for purposes of personal gain, espionage, terrorism, or revenge. While it is difficult to obtain exact statistics on computer misuse, clearly it is growing. It is also clear that insiders -- authorized system users -- are responsible for most of this increase. Unfortunately, their insider status gives them a greater potential for harm This paper takes an asset-based approach to the insider threat. We begin by characterizing the insider and the threat posed by variously motivated insiders. Next, we characterize the asset of concern: computerized information of strategic or economic value. We discuss four general ways in which computerized information is vulnerable to adversary action by the insider: disclosure, violation of integrity, denial of service, and unauthorized use of resources. We then look at three general remedies for these vulnerabilities. The first is formality of operations, such as training, personnel screening, and configuration management. The second is the institution of automated safeguards, such as single-use passwords, encryption, and biometric …
Date: January 1, 1993
Creator: Hochberg, J. G.; Jackson, K. A.; McClary, J. F. & Simmonds, D. D.
Object Type: Article
System: The UNT Digital Library
ADLIB: A simple database framework for beamline codes (open access)

ADLIB: A simple database framework for beamline codes

There are many well developed codes available for beamline design and analysis. A significant fraction of each of these codes is devoted to processing its own unique input language for describing the problem. None of these large, complex, and powerful codes does everything. Adding a new bit of specialized physics can be a difficult task whose successful completion makes the code even larger and more complex. This paper describes an attempt to move in the opposite direction, toward a family of small, simple, single purpose physics and utility modules, linked by an open, portable, public domain database framework. These small specialized physics codes begin with the beamline parameters already loaded in the database, and accessible via the handful of subroutines that constitute ADLIB. Such codes are easier to write, and inherently organized in a manner suitable for incorporation in model based control system algorithms. Examples include programs for analyzing beamline misalignment sensitivities, for simulating and fitting beam steering data, and for translating among MARYLIE, TRANSPORT, and TRACE3D formats.
Date: January 1, 1993
Creator: Mottershead, C.T.
Object Type: Article
System: The UNT Digital Library
Advanced computational methods for nodal diffusion, Monte Carlo, and S[sub N] problems (open access)

Advanced computational methods for nodal diffusion, Monte Carlo, and S[sub N] problems

This document describes progress on five efforts for improving effectiveness of computational methods for particle diffusion and transport problems in nuclear engineering: (1) Multigrid methods for obtaining rapidly converging solutions of nodal diffusion problems. A alternative line relaxation scheme is being implemented into a nodal diffusion code. Simplified P2 has been implemented into this code. (2) Local Exponential Transform method for variance reduction in Monte Carlo neutron transport calculations. This work yielded predictions for both 1-D and 2-D x-y geometry better than conventional Monte Carlo with splitting and Russian Roulette. (3) Asymptotic Diffusion Synthetic Acceleration methods for obtaining accurate, rapidly converging solutions of multidimensional SN problems. New transport differencing schemes have been obtained that allow solution by the conjugate gradient method, and the convergence of this approach is rapid. (4) Quasidiffusion (QD) methods for obtaining accurate, rapidly converging solutions of multidimensional SN Problems on irregular spatial grids. A symmetrized QD method has been developed in a form that results in a system of two self-adjoint equations that are readily discretized and efficiently solved. (5) Response history method for speeding up the Monte Carlo calculation of electron transport problems. This method was implemented into the MCNP Monte Carlo code. In addition, …
Date: January 1, 1993
Creator: Martin, W. R.
Object Type: Report
System: The UNT Digital Library
Advanced computational methods for nodal diffusion, Monte Carlo, and S{sub N} problems. Progress report, January 1, 1992--March 31, 1993 (open access)

Advanced computational methods for nodal diffusion, Monte Carlo, and S{sub N} problems. Progress report, January 1, 1992--March 31, 1993

This document describes progress on five efforts for improving effectiveness of computational methods for particle diffusion and transport problems in nuclear engineering: (1) Multigrid methods for obtaining rapidly converging solutions of nodal diffusion problems. A alternative line relaxation scheme is being implemented into a nodal diffusion code. Simplified P2 has been implemented into this code. (2) Local Exponential Transform method for variance reduction in Monte Carlo neutron transport calculations. This work yielded predictions for both 1-D and 2-D x-y geometry better than conventional Monte Carlo with splitting and Russian Roulette. (3) Asymptotic Diffusion Synthetic Acceleration methods for obtaining accurate, rapidly converging solutions of multidimensional SN problems. New transport differencing schemes have been obtained that allow solution by the conjugate gradient method, and the convergence of this approach is rapid. (4) Quasidiffusion (QD) methods for obtaining accurate, rapidly converging solutions of multidimensional SN Problems on irregular spatial grids. A symmetrized QD method has been developed in a form that results in a system of two self-adjoint equations that are readily discretized and efficiently solved. (5) Response history method for speeding up the Monte Carlo calculation of electron transport problems. This method was implemented into the MCNP Monte Carlo code. In addition, …
Date: January 1, 1993
Creator: Martin, W. R.
Object Type: Report
System: The UNT Digital Library
Advanced computers and simulation (open access)

Advanced computers and simulation

Accelerator physicists today have access to computers that are far more powerful than those available just 10 years ago. In the early 1980's, desktop workstations performed less one million floating point operations per second (Mflops), and the realized performance of vector supercomputers was at best a few hundred Mflops. Today vector processing is available on the desktop, providing researchers with performance approaching 100 Mflops at a price that is measured in thousands of dollars. Furthermore, advances in Massively Parallel Processors (MPP) have made performance of over 10 gigaflops a reality, and around mid-decade MPPs are expected to be capable of teraflops performance. Along with advances in MPP hardware, researchers have also made significant progress in developing algorithms and software for MPPS. These changes have had, and will continue to have, a significant impact on the work of computational accelerator physicists. Now, instead of running particle simulations with just a few thousand particles, we can perform desktop simulations with tens of thousands of simulation particles, and calculations with well over 1 million particles are being performed on MPPs. In the area of computational electromagnetics, simulations that used to be performed only on vector supercomputers now run in several hours on desktop …
Date: January 1, 1993
Creator: Ryne, R.D.
Object Type: Article
System: The UNT Digital Library
Advanced control system for the Integral Fast Reactor fuel pin processor (open access)

Advanced control system for the Integral Fast Reactor fuel pin processor

A computerized control system has been developed for the remotely-operated fuel pin processor used in the Integral Fast Reactor Program, Fuel Cycle Facility (FCF). The pin processor remotely shears cast EBR- reactor fuel pins to length, inspects them for diameter, straightness, length, and weight, and then inserts acceptable pins into new sodium-loaded stainless-steel fuel element jackets. Two main components comprise the control system: (1) a programmable logic controller (PLC), together with various input/output modules and associated relay ladder-logic associated computer software. The PLC system controls the remote operation of the machine as directed by the OCS, and also monitors the machine operation to make operational data available to the OCS. The OCS allows operator control of the machine, provides nearly real-time viewing of the operational data, allows on-line changes of machine operational parameters, and records the collected data for each acceptable pin on a central data archiving computer. The two main components of the control system provide the operator with various levels of control ranging from manual operation to completely automatic operation by means of a graphic touch screen interface.
Date: January 1, 1993
Creator: Lau, L. D.; Randall, P. F.; Benedict, R. W. & Levinskas, D.
Object Type: Article
System: The UNT Digital Library
Advanced metering techniques (open access)

Advanced metering techniques

The goal of the US Department of Energy Federal Energy Management Program (FEMP) is to facilitate energy-efficiency improvements at federal facilities. This is accomplished by a balanced program of technology development, facility assessment, and use of cost-sharing procurement mechanisms. Technology development focuses upon the tools and procedures used to identify and evaluate efficiency improvements. For facility assessment, FEMP provides metering equipment and trained analysts to federal agencies exhibiting a commitment to improve energy-use efficiency. To assist in implementing energy-efficiency measures, FEMP helps federal agencies with identifying efficiency opportunities and in implementing energy-efficiency and demand-side management programs at federal sites. As the lead laboratory for FEMP, Pacific Northwest Laboratory (PNL) provides technical assistance to federal agencies to better understand and characterize energy systems. The US Army Forces Command (FORSCOM) has tasked PNL to provide technical assistance to characterize and modernize energy systems at FORSCOM installations. As part of that technical assistance, PNL performed an in-depth examination of automatic meter-reading system technologies currently available. The operating characteristics and relative merits of all the major systems were reviewed in the context of applicability to federal installations. That review is documented in this report.
Date: January 1, 1993
Creator: Szydlowski, R.F.
Object Type: Report
System: The UNT Digital Library
Advanced metering techniques (open access)

Advanced metering techniques

The goal of the US Department of Energy Federal Energy Management Program (FEMP) is to facilitate energy-efficiency improvements at federal facilities. This is accomplished by a balanced program of technology development, facility assessment, and use of cost-sharing procurement mechanisms. Technology development focuses upon the tools and procedures used to identify and evaluate efficiency improvements. For facility assessment, FEMP provides metering equipment and trained analysts to federal agencies exhibiting a commitment to improve energy-use efficiency. To assist in implementing energy-efficiency measures, FEMP helps federal agencies with identifying efficiency opportunities and in implementing energy-efficiency and demand-side management programs at federal sites. As the lead laboratory for FEMP, Pacific Northwest Laboratory (PNL) provides technical assistance to federal agencies to better understand and characterize energy systems. The US Army Forces Command (FORSCOM) has tasked PNL to provide technical assistance to characterize and modernize energy systems at FORSCOM installations. As part of that technical assistance, PNL performed an in-depth examination of automatic meter-reading system technologies currently available. The operating characteristics and relative merits of all the major systems were reviewed in the context of applicability to federal installations. That review is documented in this report.
Date: January 1, 1993
Creator: Szydlowski, R. F.
Object Type: Report
System: The UNT Digital Library
Advanced Neutron Source (ANS) Project progress report FY 1992 (open access)

Advanced Neutron Source (ANS) Project progress report FY 1992

This report discusses project management, research and development, design, and safety at the Advanced Neutron Source facility.
Date: January 1, 1993
Creator: Campbell, J. H.; Selby, D. L. & Harrington
Object Type: Report
System: The UNT Digital Library
Advanced Neutron Source (ANS) Project progress report FY 1992 (open access)

Advanced Neutron Source (ANS) Project progress report FY 1992

This report discusses project management, research and development, design, and safety at the Advanced Neutron Source facility.
Date: January 1, 1993
Creator: Campbell, J. H.; Selby, D. L. & Harrington.
Object Type: Report
System: The UNT Digital Library