Development of a High Performance Storage System (HPSS) (open access)

Development of a High Performance Storage System (HPSS)

The overall objective of the project was the development of a parallel high performance storage software package capable of data transfer rates above 1 gigabyte/see with files of essentially unlimited size. This necessitated modules for uniquely identifying files to be stored, for establishing the appropriate locale for the file in the storage hardware, for moving the file in parallel to the selected lode, and for making possible ready access to the file when desired. And all of this must be done with absolute accuracy and reliability while ensuring security at the requisite level. Responsibility for the various modules was distributed across the participating laboratories. The central LMER responsibility was the Storage System Management (SSM) package, the software package that controls all storage and access activities and provides readily understandable and complete information concerning system status to an operator. This information includes storage and access activity in progress; the location, size, and character of all files; and warning and error messages, among others. As such, SSM must be tightly coordinated with all of the HPSS modules and components and must represent in effect, a synthesis of all. The result of this very extensive LMER effort was an SSM system that required …
Date: December 27, 1996
Creator: Kliewer, K. L.
Object Type: Report
System: The UNT Digital Library
Reynolds Number in MAGCOOL Subcooler (open access)

Reynolds Number in MAGCOOL Subcooler

None
Date: June 27, 1996
Creator: C., Wu K.
Object Type: Report
System: The UNT Digital Library
SECOND WASTE PACKAGE PROBABILISTIC CRITICALITY ANALYSIS: GENERATION AND EVALUATION OF INTERNAL CRITICIALITY CONFIGURATIONS (open access)

SECOND WASTE PACKAGE PROBABILISTIC CRITICALITY ANALYSIS: GENERATION AND EVALUATION OF INTERNAL CRITICIALITY CONFIGURATIONS

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide an evaluation of the criticality potential within a waste package having sonic or all of its contents degraded by corrosion and removal of neutron absorbers. This analysis is also intended to provide an estimate of the consequences of any internal criticality, particularly in terms of any increase in radionuclide inventory. These consequence estimates will be used as part of the WPD input to the Total System Performance Assessment. The ultimate objective of this analysis is to augment the information gained from the Initial Waste Package Probabilistic Criticality Analyses (Ref. 5.8 and 5.9, hereafter referred to as IPA) to a degree which will support preliminary waste package design recommendations intended to reduce the risk of waste package criticality and the risk to total repository system performance posed by the consequences of any criticality. The IPA evaluated the criticality potential under the assumption that the waste package basket retained its structural integrity, so that the assemblies retained their initial separation, even when the neutron absorbers had been leached from the basket. This analysis is based on the more realistic condition that removal of the …
Date: March 27, 1996
Creator: P. Gottlieb, J.R. Massari, J.K. McCoy
Object Type: Report
System: The UNT Digital Library
Corrective Action Investigation Plan: Roller Coaster Lagoons and North Disposal Trench, Tonopah Test Range, Revision 1 (open access)

Corrective Action Investigation Plan: Roller Coaster Lagoons and North Disposal Trench, Tonopah Test Range, Revision 1

1.1 Purpose The purpose of this investigation is to collect data to confirm the presence or absence of contamination, evaluate the potential for contaminant migration, and select appropriate closure methods for these sites. The potential closure methods for these sites involve either clean closure, closure in place, or no further action. 1.2 Scope The scope of this investigation includes collecting surface and subsurface soil samples at the Roller Coaster Lagoons; and collecting surface soil samples at the North Disposal Trench and the small spill area associated with the Voluntary Cotiective Action (VCA) that was conducted in 1995.
Date: June 27, 1996
Creator: IT Corporation, Las Vegas, NV
Object Type: Report
System: The UNT Digital Library
Chaotic behavior control in fluidized bed systems using artificial neural network. Quarterly progress report, October 1, 1996--December 31, 1996 (open access)

Chaotic behavior control in fluidized bed systems using artificial neural network. Quarterly progress report, October 1, 1996--December 31, 1996

Pressurized fluidized-bed combustors (FBC) are becoming very popular, efficient, and environmentally acceptable replica for conventional boilers in Coal-fired and chemical plants. In this paper, we present neural network-based methods for chaotic behavior monitoring and control in FBC systems, in addition to chaos analysis of FBC data, in order to localize chaotic modes in them. Both of the normal and abnormal mixing processes in FBC systems are known to undergo chaotic behavior. Even though, this type of behavior is not always undesirable, it is a challenge to most types of conventional control methods, due to its unpredictable nature. The performance, reliability, availability and operating cost of an FBC system will be significantly improved, if an appropriate control method is available to control its abnormal operation and switch it to normal when exists. Since this abnormal operation develops only at certain times due to a sequence of transient behavior, then an appropriate abnormal behavior monitoring method is also necessary. Those methods has to be fast enough for on-line operation, such that the control methods would be applied before the system reaches a non-return point in its transients. It was found that both normal and abnormal behavior of FBC systems are chaotic. However, …
Date: February 27, 1996
Creator: Bodruzzaman, M. & Essawy, M.A.
Object Type: Report
System: The UNT Digital Library
Summary of raman cone penetrometer probe waste tank radiation and chemical environment test (open access)

Summary of raman cone penetrometer probe waste tank radiation and chemical environment test

This report summarizes the results of testing Raman sapphire windows that were braze mounted into a mockup Raman probe head and stainless steel coupons in a simulated tank waste environment. The simulated environment was created by exposing sapphire window components, immersed in a tank simulant, in a gamma pit. This work was completed for the U.S. Department of Energy (DOE) Office of Environmental Management (EM-50) for Technical Task Proposal RL4-6-WT-21.
Date: September 27, 1996
Creator: Reich, F.R.
Object Type: Report
System: The UNT Digital Library
Investigation and demonstration of dry carbon-based sorbent injection for mercury control. Quarterly technical report, April 1--June 30, 1996 (open access)

Investigation and demonstration of dry carbon-based sorbent injection for mercury control. Quarterly technical report, April 1--June 30, 1996

The overall objective this two phase program is to investigate the use of dry carbon-based sorbents for mercury control. During Phase 1, a bench-scale field test device that can be configured as an electrostatic precipitator, a pulse-jet baghouse, or a reverse-gas baghouse has been designed and will be integrated with an existing pilot-scale facility at PSCo`s Comanche Station. Up to three candidate sorbents will then be injected into the flue gas stream upstream of the test device to determine the mercury removal efficiency for each sorbent. During the Phase 11 effort, component integration for the most promising dry sorbent technology (technically and economically feasible) shall be tested at the 5000 acfm pilot-scale. An extensive work plan has been developed for the project. Three sorbents will be selected for evaluation at the facility through investigation, presentation, and discussion among team members: PSCO, EPRI, ADA, and DOE. The selected sorbents will be tested in the five primary bench-scale configurations: pulse `et baghouse, TOXECON, reverse-gas baghouse, electrostatic precipitator, and an ESP or fabric filter `with no Comanche ash in the flue gas stream. In the EPRI TOXECON system, mercury sorbents will be injected downstream of a primary particulate control device, and collected in …
Date: July 27, 1996
Creator: Hunt, T.; Sjostrom, S.; Smith, J. & Chang, R.
Object Type: Report
System: The UNT Digital Library
TCP performance in ATM networks: ABR parameter tuning and ABR/UBR comparisons (open access)

TCP performance in ATM networks: ABR parameter tuning and ABR/UBR comparisons

This paper explores two issues on TOP performance over ATM networks: ABR parameter tuning and performance comparison of binary mode ABR with enhanced UBR services. Of the fifteen parameters defined for ABR, two parameters dominate binary mode ABR performance: Rate Increase Factor (RIF) and Rate Decrease Factor (RDF). Using simulations, we study the effects of these two parameters on TOP over ABR performance. We compare TOP performance with different ABR parameter settings in terms of through-puts and fairness. The effects of different buffer sizes and LAN/WAN distances are also examined. We then compare TOP performance with the best ABR parameter setting with corresponding UBR service enhanced with Early Packet Discard and also with a fair buffer allocation scheme. The results show that TOP performance over binary mode ABR is very sensitive to parameter value settings, and that a poor choice of parameters can result in ABR performance worse than that of the much less expensive UBR-EPD scheme.
Date: February 27, 1996
Creator: Chien Fang & Lin, A.
Object Type: Article
System: The UNT Digital Library
Hanford tanks initiative work plan -- subsurface characterization to support the closure-readiness demonstration for tank 241-AX-104 (open access)

Hanford tanks initiative work plan -- subsurface characterization to support the closure-readiness demonstration for tank 241-AX-104

This document presents a plan for subsurface investigation near 241-AX-104 Single-Shell tank. Objectives of the investigation are soil sampling and analyses (physical and chemical), local stratigraphic correlation, groundwater background characterization, and geophysical surveys. The primary purpose of the investigation is to supply physical and hydraulic properties for numerical modeling of vadose zone flow and transport.
Date: September 27, 1996
Creator: Barnett, D. B.
Object Type: Report
System: The UNT Digital Library
Generation of partially coherent stationary time histories with non-Gaussian distributions (open access)

Generation of partially coherent stationary time histories with non-Gaussian distributions

In a previous paper Smallwood and Paez (1991) showed how to generate realizations of partially coherent stationary normal time histories with a specified cross-spectral density matrix. This procedure is generalized for the case of multiple inputs with a specified cross-spectral density function and a specified marginal probability density function (pdf) for each of the inputs. The specified pdfs are not required to be Gaussian. A zero memory nonlinear (ZMNL) function is developed for each input to transform a Gaussian or normal time history into a time history with a specified non-Gaussian distribution. The transformation functions have the property that a transformed time history will have nearly the same auto spectral density as the original time history. A vector of Gaussian time histories are then generated with the specified cross-spectral density matrix. These waveforms are then transformed into the required time history realizations using the ZMNL function.
Date: August 27, 1996
Creator: Smallwood, D.O.
Object Type: Article
System: The UNT Digital Library
International petroleum statistics report, September 1996 (open access)

International petroleum statistics report, September 1996

The International Petroleum Statistics Report presents data on international oil production, demand, imports, and stocks. The report has four sections. Section 1 contains time series data on world oil production, and on oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). This section contains annual data beginning in 1985, and monthly data for the most recent two years. Section 2 presents an oil supply/demand balance for the world. This balance is presented in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. This section contains annual data for the most recent year, quarterly data for the most recent two quarters, and monthly data for the most recent twelve months. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries. World oil production and OECD demand data are for the years 1970 through 1995; OECD stocks from 1973 through 1995; and OECD trade from 1985 through 1995.
Date: September 27, 1996
Creator: unknown
Object Type: Report
System: The UNT Digital Library
High level waste interim storge architecture selection - decision report (open access)

High level waste interim storge architecture selection - decision report

The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities (RL 1996a). This plan contains a two-phased approach. Phase I is a proof-of-principle/connnercial demonstration- scale effort and Phase II is a fiill-scale production effort. In accordance with the planned approach, interim storage and disposal of various products from privatized facilities are to be DOE fumished. The high-level waste (BLW) interim storage options, or alternative architectures, were identified and evaluated to provide the framework from which to select the most viable method of Phase I BLW interim storage (Calmus 1996). This evaluation, hereafter referred to as the Alternative Architecture Evaluation, was performed to established performance and risk criteria (technical merit, cost, schedule, etc.). Based on evaluation results, preliminary architectures and path forward reconunendations were provided for consideration in the architecture decision- maldng process. The decision-making process used for selection of a Phase I solidified BLW interim storage architecture was conducted in accordance with an approved Decision Plan (see the attachment). This decision process was based on TSEP-07,Decision Management Procedure (WHC 1995). The established decision process entailed a Decision Board, consisting of Westinghouse Hanford Company (VY`HC) management staff, …
Date: September 27, 1996
Creator: Calmus, R. B.
Object Type: Report
System: The UNT Digital Library
Computer-Aided dispatching system design specification (open access)

Computer-Aided dispatching system design specification

This document defines the performance requirements for a graphic display dispatching system to support Hanford Patrol emergency response. This document outlines the negotiated requirements as agreed to by GTE Northwest during technical contract discussions. This system defines a commercial off-the-shelf computer dispatching system providing both test and graphic display information while interfacing with diverse alarm reporting system within the Hanford Site. This system provided expansion capability to integrate Hanford Fire and the Occurrence Notification Center. The system also provided back-up capability for the Plutonium Processing Facility (PFP).
Date: September 27, 1996
Creator: Briggs, M. G.
Object Type: Report
System: The UNT Digital Library
High level waste storage tanks 242-A evaporator S/RID phase II assessment report (open access)

High level waste storage tanks 242-A evaporator S/RID phase II assessment report

This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.
Date: September 27, 1996
Creator: Biebesheimer, E.
Object Type: Report
System: The UNT Digital Library
Remote nuclear screening system for hostile environments (open access)

Remote nuclear screening system for hostile environments

A remote measurement system has been constructed for in situ gamma and beta isotopic characterization of highly radioactive nuclear material in hostile environments. A small collimated, planar CdZnTe detector is used for gamma-ray spectroscopy. Spectral resolution of 2% full width at half maximum at 662 kiloelectronvolts has been obtained remotely using rise time compensation and limited pulse shape discrimination, Isotopc measurement of high-energy beta emitters was accomplished with a ruggedized, deeply depleted, surface barrier silicon dictator. The primary function of the remote nuclear screening system is to provide fast qualitative and quantitative isotopic assessment of high-level radioactive material.
Date: February 27, 1996
Creator: Addleman, R. S.; Beck, M. A.; Blewett, G. R.; Selle, E. R.; McClellan, C. S.; Dodd, D. A. et al.
Object Type: Report
System: The UNT Digital Library
340 and 310 drawing field verification (open access)

340 and 310 drawing field verification

The purpose of the drawing field verification work plan is to provide reliable drawings for the 310 Treated Effluent Disposal Facility (TEDF) and 340 Waste Handling Facility (340 Facility). The initial scope of this work plan is to provide field verified and updated versions of all the 340 Facility essential drawings. This plan can also be used for field verification of any other drawings that the facility management directs to be so updated. Any drawings revised by this work plan will be issued in an AutoCAD format.
Date: September 27, 1996
Creator: Langdon, J.
Object Type: Report
System: The UNT Digital Library
Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflagration (open access)

Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflagration

The purpose of this calculation note is to provide the basis for In-Tank Fuel Fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided.
Date: September 27, 1996
Creator: Crowe, R.D.
Object Type: Report
System: The UNT Digital Library
Maintenance implementation plan for solid waste management (open access)

Maintenance implementation plan for solid waste management

This Maintenance Implementation Plan (MIP)was developed for implementation of the U.S. Department of Energy (DOE) Order 4330.4A, A Maintenance Implementation Program (DOE 1990) which has been replaced by 4330.4B (DOE 1994) at the Hanford Site SWM complex. It addresses maintenance functions associated with SWM, which includes the field operational group and the facilities operational group. An assessment of the existing maintenance programs for SWM was performed, and the results of this assessment were evaluated to determine corrective actions required to bring Solid Waste Maintenance into compliance with the order. The objective of this MIP is to provide baseline information for the control and execution of SWM Maintenance activities relative to the requirements of Order 4330.4B, Chapter II. (Nuclear Facilities) It also describes actions that are planned to achieve compliance. Section 2.0 of this MIP summarizes the mission, history, and future plans of SWM. Section 3.0 describes maintenance scope and requirements, and outlines the overall strategy (both near- term and long-term) for implementing improvements to the maintenance program. Specific elements of DOE Order 4330.4B are addressed in Section 4.0, including objectives of each element, a discussion of how SWM addresses these objectives, proposed improvements, and references to Westinghouse Hanford Company (Westinghouse …
Date: June 27, 1996
Creator: Reddinger, R.W., Westinghouse Hanford
Object Type: Report
System: The UNT Digital Library
Strategy of Resolution of the Organic Complexant and Organic Solvent Safety Issues (open access)

Strategy of Resolution of the Organic Complexant and Organic Solvent Safety Issues

A basic strategy and logic for resolving the organic complexant and organic solvent safety issues are presented. Interim safe storage can be ensured in one of three ways: demonstrate through theory, modeling, sampling, and testing that the waste lacks sufficient fuel to combust; show through modeling and monitoring that the waste contains sufficient moisture to prevent ignition and combustion; or demonstrate that ignition sources are adequately controlled. Mitigation is required if controls are deemed inadequate. Presently, no single alternative is believed sufficient to ensure interim safe storage for all organic tanks. Therefore, activities for all three alternatives are summarized in this strategy.
Date: June 27, 1996
Creator: Meacham, J. E.
Object Type: Report
System: The UNT Digital Library
The effects of load drop, uniform load and concentrated loads on waste tanks (open access)

The effects of load drop, uniform load and concentrated loads on waste tanks

This document provides the supporting calculations performed by others specifically for the TWRS FSAR and more detailed summaries of the important references issued in the past regarding the effects of various loads.
Date: September 27, 1996
Creator: Marusich, R.M.
Object Type: Report
System: The UNT Digital Library
HEPA filter failure by fire or heater overtemperature and subsequent unfiltered release (open access)

HEPA filter failure by fire or heater overtemperature and subsequent unfiltered release

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report.
Date: December 27, 1996
Creator: Ryan, G. W.
Object Type: Report
System: The UNT Digital Library
Engineering study of tank fill options for landfill closure (open access)

Engineering study of tank fill options for landfill closure

To prepare single-shell tanks for closure, it will be necessary to piece some type of load- bearing fill material inside the tanks to support the domes. Provision of internal support permits the simplifying assumption that the combined weight of the dome, the existing operational soil cover, and the surface barrier will eventually transfer to and be carried by the fill. This engineering study provides descriptions and evaluations of four alternative concepts for fitting and stabilizing nominally empty SSTs with fill materials. For this study it is assumed that 99 percent (or more) of tank wastes will be retrieved before closure is undertaken. The alternatives are: Gravel: tanks would be fitted with crushed aggregate using a rotating stinger apparatus installed in the central riser; Grout: tanks would be fitted with a pumpable, ex-situ mixed grout formulation; Hybrid: tanks would be fitted first with coarse aggregate, then with grout, producing a pre-placed aggregate concrete material; or Concrete: tank. would be filled with a highly-flowable, ex-situ mixed concrete formulation.
Date: September 27, 1996
Creator: Skelly, W. A.
Object Type: Report
System: The UNT Digital Library
HEPA filter fire (and subsequent unfiltered release) (open access)

HEPA filter fire (and subsequent unfiltered release)

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: HEPA Filter Failure - Exposure to High Temperature or Pressure. The calculations needed to quantify the risk associated with this accident scenario are included within.
Date: September 27, 1996
Creator: Powers, T. B.
Object Type: Report
System: The UNT Digital Library
340 Waste handling facility deactivation plan (open access)

340 Waste handling facility deactivation plan

This document provides an overview of both the present status of the 340 Complex (within Hanford`s 300 Area), and of tasks associated with the deactivation of segments associated with radioactive, mixed liquid waste receipt, storage, and shipping. The plan also describes activities that will allow portions of the 340 Complex to remain in service.
Date: December 27, 1996
Creator: Stordeur, R.T., Westinghouse Hanford
Object Type: Report
System: The UNT Digital Library