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A trainer's role in effecting a cultural change

Description: Teaching is a process used to bring about a change in a person or target group for the benefit of that individual, society, or the organization. The trainer's role in effecting a cultural change is not as a teacher of cultural behaviors but as a facilitator of cultural change. This paper will concentrate primarily on the analysis, solicitation of management support, and implementation phases of effecting a cultural change among a target group from the trainer's side of the process. The three ma… more
Date: November 1, 1991
Creator: Hopkins, G.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Preliminary upper axial shield design for space reactor ground test

Description: A prototype of the SP-100 space reactor will be tested in a vacuum environment on the ground to verify the design prior to flight applications. Neutronic calculations are under way to design shielding that will provide the appropriate operational protection for both personnel and instrumentation, and will not compromise any important flight-type conditions of the reactor and shield system. This document describes the preliminary design of the shielding system. 1 ref., 11 figs.
Date: November 1, 1987
Creator: Carter, L. L. & Bunch, W. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Materials evaluation for a transuranic processing facility

Description: The Westinghouse Hanford Company, with the assistance of the Pacific Northwest Laboratory, is developing a transuranium extraction process for preheating double-shell tank wastes at the Hanford Site to reduce the volume of transuranic waste being sent to a repository. The bench- scale transuranium extraction process development is reaching a stage where a pilot plant design has begun for the construction of a facility in the existing B Plant. Because of the potential corrosivity of neutralized … more
Date: November 1, 1990
Creator: Barker, S.A., Schwenk, E.B. (Westinghouse Hanford Co., Richland, WA (USA)) & Divine, J.R. (Pacific Northwest Lab., Richland, WA (USA))
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Partner: UNT Libraries Government Documents Department
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Fracture toughness evaluation for N Reactor pressure tubes of Zircaloy-2 using the electric-potential method

Description: Zircaloy is commonly used for the cladding or pressure tubes in commercial reactors because of its strength, corrosion resistance, and low absorption of thermal neutrons. Fracture toughness test techniques using small samples fabricated from archival materials from N Reactor pressure tubes of Zircaloy-2 were developed to study the factors affecting tube fracture toughness. Compact tension specimen thickness was limited by the wall thickness (7 mm) of the tubes. Specimens (5 mm thick) were prepa… more
Date: November 1, 1991
Creator: Huang, F.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility sodium pump operating experience - mechanical

Description: The Heat Transport System (HTS) pumps were designed, fabricated, tested, and installed in the Fast Flux Test Facility (FFTF) Plant during the period from September 1970 through July 1977. Since completion of the installation and sodium fill in December 1978, the FFTF Plant pumps have undergone extensive testing and operation with HTS testing and reactor operation. Steady-state hydraulic and mechanical performances have been and are excellent. In all, FFTF primary and secondary pumps have operat… more
Date: November 1, 1987
Creator: Buonamici, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An overview of Hanford site waste cleanup

Description: Waste cleanup at the Hanford Site involves actions leading to the disposal of all radioactive and hazardous wastes, managed by the Waste Management Program, and the remediation of inactive sites and facilities, managed by the Environmental Restoration Program. The Waste Management Program consists of five missions: double-shell tank wastes, single-shell tank wastes, encapsulated cesium and strontium, solid wastes (SW), and liquid effluents. A general category of program support is also included… more
Date: November 1, 1989
Creator: Merrick, D.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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On-Line Measurement of Stack-Gas Particulate Radionuclides

Description: This paper describes an advanced process-monitoring system for the automatic sample collection, analysis, reporting, and alarming of the concentration of long-lived radionuclides in nuclear process stack-gas effluents. This system, the Moving Filter Radioactive Aerosol Monitor, collects particulates in a conditioned sampling chamber, under computer control, for subsequent and separate alpha and beta counting and analysis. The alpha measurement is performed with a solid-state surface-barrier det… more
Date: November 1987
Creator: Stong, F. S.; Troyer, G. L. & Criddle, J. D., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility interim examination and maintenance cell contaminated sodium recovery system: Remote handling design consideration

Description: The Westinghouse Hanford Company is installing a remotely operated Contaminated Sodium Recovery System (CSRS) at the Fast Flux Test Facility (FFTF) located in Richland, Washington. The CSRS will recover activated sodium that accumulates in fuel transfer machines during core component transfer operations. Drip pots from the FFTF fuel handling machines will be delivered to the shielded, argon-inerted Interim Examination and Maintenance (IEM) Cell, a hot cell located in the FFTF containment struct… more
Date: November 1, 1988
Creator: Carteret, B. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Performance analysis of a mixed nitride fuel system for an advanced liquid metal reactor

Description: The conceptual development and analysis of a proposed mixed nitride driver and blanket fuel system for a prototypic advanced liquid metal reactor design has been performed. As a first step, an intensive literature survey was completed on the development and testing of nitride fuel systems. Based on the results of this survey, prototypic mixed nitride fuel and blanket pins were designed and analyzed using the SIEX computer code. The analysis predicted that the nitride fuel consistently operated … more
Date: November 1, 1990
Creator: Lyon, W.F.; Baker, R.B. & Leggett, R.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility core system

Description: A review of Liquid Metal Reactor (LMR) core system accomplishments provides an excellent road map through the maze of issues that faced reactor designers 10 years ago. At that time relatively large uncertainties were associated with fuel pin and fuel assembly performance, irradiation of structural materials, and performance of absorber assemblies. The extensive core systems irradiation program at the US Department of Energy's Fast Flux Test Facility (FFTF) has addressed each of these principal … more
Date: November 1, 1990
Creator: Ethridge, J.L. (Pacific Northwest Lab., Richland, WA (USA)); Baker, R.B.; Leggett, R.D.; Pitner, A.L. & Waltar, A.E. (Westinghouse Hanford Co., Richland, WA (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Remote removal of an obstruction from FFTF (Fast Flux Test Facility) in-service inspection camera track

Description: Remote techniques and special equipment were used to clear the path of a closed-circuit television camera system that travels on a monorail track around the reactor vessel support arm structure. A tangle of wire-wrapped instrumentation tubing had been inadvertently inserted through a dislocated guide-tube expansion joint and into the camera track area. An externally driven auger device, mounted on the track ahead of the camera to view the procedure, was used to retrieve the tubing. 6 figs.
Date: November 1, 1990
Creator: Gibbons, P.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of Core Damage Frequency Due to External Events at the DOE (Department of Energy) N-Reactor

Description: A complete external events probabilistic risk assessment has been performed for the N-Reactor power plant, making full use of all insights gained during the past ten years' developments in risk assessment methodologies. A detailed screening analysis was performed which showed that all external events had negligible contribution to core damage frequency except fires, seismic events, and external flooding. A limited scope analysis of the external flooding risk indicated that it is not a major ris… more
Date: November 1, 1990
Creator: Lambright, J. A.; Bohn, M. P.; Daniel, S. L.; Baxter, J. T.; Johnson, J. J.; Ravindra, M. K. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A decade of radiological and shielding experience at the Fast Flux Test Facility

Description: The Fast Flux Test Facility (FFTF) has operated for almost a decade after first going critical during February 1980. Based on about 2,000 effective full-power days of operation, it is concluded that radiological safety can be achieved in large liquid metal-cooled fast reactors. The collective dose equivalents received by operating personnel are significantly lower than those received at commercial light water reactors. No major contamination problems have been encountered in operating and maint… more
Date: November 1, 1990
Creator: Bunch, W. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Ferrocyanide Safety Project: Subtask 3. 4, Aging Studies

Description: The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. This annual report gives the results of the work co… more
Date: November 1, 1992
Creator: Lilga, M.A.; Lumetta, M.R.; Riemath, W.F.; Romine, R.A. & Schiefelbein, G.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Hanford Site generic component failure-rate database compared with other generic failure-rate databases

Description: The Risk Assessment Technology Group, Westinghouse Hanford Company (WHC), has compiled a component failure rate database to be used during risk and reliability analysis of nonreactor facilities. Because site-specific data for the Hanford Site are generally not kept or not compiled in a usable form, the database was assembled using information from a variety of other established sources. Generally, the most conservative failure rates were chosen from the databases reviewed. The Hanford Site data… more
Date: November 1, 1992
Creator: Reardon, M. F. & Zentner, M. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Definitive design report: Design report project W-025, Radioactive Mixed Waste (RMW) Land Disposal Facility NON-DRAG-OFF. Revision 1, Volume 1 and 2

Description: The purpose of this report is to describe the definitive design of the Radioactive Mixed Waste (RMW) Non-Drag-Off disposal facility, Project W-025. This report presents a n of the major landfill design features and a discussion of how each of the criteria is addressed in the design. The appendices include laboratory test results, design drawings, and individual analyses that were conducted in support of the design. Revision 1 of this document incorporates design changes resulting from an increa… more
Date: November 29, 1994
Creator: Roscha, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tritium emissions from 200 East Area Double-Shell Tanks

Description: This document evaluates the need for tritium sampling of the emissions from the 200 East Area Double Shell Tanks based on the requirements of {open_quotes}National Emission Standards for Hazardous Air Pollutants{close_quotes} (NESHAP). The NESHAP requirements are specified in 40 Code of Federal Regulation (CFR), Part 61, Subpart H; {open_quotes}National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities{close_quotes}.
Date: November 28, 1994
Creator: Bachand, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instructions for borehole sampling

Description: Geologic systems generally are complex with physical properties and trends that can be difficult to predict. Subsurface geology exerts a fundamental control on groundwater flow and contaminant transport. The primary source for direct observation of subsurface geologic information is a borehole. However, direct observations from a borehole essentially are limited to the diameter and spacing of boreholes and the quality of the information derived from the drilling. Because it is impractical to dr… more
Date: November 11, 1994
Creator: Reynolds, K. D. & Lindsey, K. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering test plan for Tank 241-SY-101 in situ viscometer

Description: To obtain in situ measurements of the rheological properties within tank 241-SY-101, this document will implement the test strategy defined in PNLMIT-041994, acquisition and Reduction of Data Obtained in Tank SY-101 with the Ball Rheometer. Instructions for all sequences are defined within the procedure. All safety requirements as defined in LA-UR-92-3196, A Safety Assessment for Proposed Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-101-SY have been implemented into this proc… more
Date: November 1, 1994
Creator: Sobocinski, R. G.; Stokes, T. I. & Pearce, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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200 Area TEDF interface control document

Description: Because the TEDF does not have any treatment or retention capacity, strict control at the generator interface is essential to operate the TEDF in compliance with good engineering practices, Hanford site requirements, and the 216 Discharge Permit. The information in the Interface Control Document (ICD) forms the basis of understanding between all parties involved in the TEDF; DOE, WHC, and the generating facilities. The ICD defines the controlling document hierarchy; LEF, and generator responsib… more
Date: November 15, 1994
Creator: Brown, M. J. & Hildebrand, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Functional design criteria for Project W-252, Phase II Liquid Effluent Treatment and Disposal: Revision 1

Description: This document provides the functional design criteria required for the Phase 2 Liquid Effluent Treatment and Disposal Project, Project W-252. Project W-252 shall provide new facilities and existing facility modifications required to implement Best Available Technology/All Known, Available, and Reasonable Methods of Prevention, Control, and Treatment (BAT/AKART) for the 200 East Phase II Liquid Effluent Streams. The project will also provide a 200 East Area Phase II Effluent Collection System (P… more
Date: November 10, 1994
Creator: Hatch, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Configuration management program plan for Hanford site systems engineering

Description: This plan establishes the integrated configuration management program for the evolving technical baseline developed through the systems engineering process. This configuration management program aligns with the criteria identified in the DOE Standard, DOE-STD-1073-93. Included are specific requirements for control of the systems engineering RDD-100 database, and electronic data incorporated in the database that establishes the Hanford site technical baseline.
Date: November 14, 1994
Creator: Hoffman, A. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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45-Day deliverable for Tank 241-BX-105 Auger samples, risers 2 and 6

Description: Two auger samples from single-shell tank 241-BX-105 (BX-105) were extruded, broken down, and analyzed for DSC, TGA, and total alpha as prescribed. Analytical results were tracked and reported using the laboratory information management system known as LabCore. This is the final report for the fiscal year 1995 BX-105 auger sample characterization effort. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analyses (TGA) scans as requested. Also included is a … more
Date: November 16, 1994
Creator: Bell, K. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acid digestion demonstration (WeDID)

Description: Acid digestion process development began at the Hanford Site in 1972 with a beaker of laboratory acid and progressed through laboratory and pilot-scale development culminating in the Radioactive Acid Digestion Test Unit (RADTU). The RADTU was operational from 1977 through 1982 and processed over 5,000 kg of synthetic and combustible waste forms from Hanford Site operations. It routinely reacted plastics, wood, paper, cloth, ion-exchange resins, metals, and solvents. Operation of RADTU routinely… more
Date: November 1, 1993
Creator: Crippen, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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