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Absolute Intensities of the Vacuum Ultraviolet Spectra in a Metal-Etch Plasma Processing Discharge

Description: In this paper we report absolute intensities of vacuum ultraviolet and near ultraviolet emission lines (4.8 eV to 18 eV ) for aluminum etching discharges in an inductively coupled plasma reactor. We report line intensities as a function of wafer type, pressure, gas mixture and rf excitation level. IrI a standard aluminum etching mixture containing C12 and BC13 almost all the light emitted at energies exceeding 8.8 eV was due to neutral atomic chlorine. Optical trapping of the WV radiation in th… more
Date: December 9, 1998
Creator: Woodworth, J. R.; Blain, M. G.; Jarecki, R. L.; Hamilton, T. W. & Aragon, B. P.
Partner: UNT Libraries Government Documents Department
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FFTF Plant transition function analysis report

Description: The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and function hierarchy charts that describe what needs to be performed to deactivate FFTF.
Date: September 1, 1995
Creator: Lund, D. P.
Partner: UNT Libraries Government Documents Department
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Technical Assistance in Review of Source Term-Related Issues of Advanced Reactors

Description: The distribution of iodine in containment during an AP-600 design-basis accident was evaluated using models in the "TRENDS" code. The AP-6003BE accident sequmce calculations showed that a pH >7 was maintained for at least 30 days. Because the pH was maintained at this level, most of the iodine was in the form of iodid~ only 3 x 10-3% was present as aqueous 12, and only 1 x 10< `/0 was present as J in the vapor phase.
Date: October 1, 1998
Creator: Beahm, E.C.; Dillow, T.A. & Weber, C.F.
Partner: UNT Libraries Government Documents Department
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Analyses of a Reinforced Concrete Containment with Liner Corrosion Damage

Description: Incidents of liner corrosion in nuclear power containment structures have been recorded. These incidents and concerns of other possible liner corrosion in containment have prompted an interest in determining g the capacity of a degraded containment. Finite element analyses of a typical pressurized water reactor (PWR) reinforced concrete containment with liner corrosion were conducted using the A13AQUS finite element code with the ANACAP-U nonlinear concrete constitutive model. The effect of lin… more
Date: November 19, 1998
Creator: Cherry, J. L. & Smith, J. A.
Partner: UNT Libraries Government Documents Department
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FFTF Plant transition mission analysis report

Description: FFTF (Fast Flux Test Facility) is a 400-MW(t) sodium-cooled, fast flux test reactor at Hanford, designed to test fuels and materials for advanced nuclear power plants; it has no capability for generating electric power. Since a long-term mission could not be found for FFTF, it was placed in standby, and a recommendation was made that it be shut down. Purpose of the FFTF Transition Project is to prepare it for Decontamination and Decommissioning; this will be accomplished by establishing a passi… more
Date: May 25, 1995
Creator: Lund, D. P.
Partner: UNT Libraries Government Documents Department
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IN-CELL visual examinations of K east fuel elements

Description: Nine outer fuel elements were recovered from the K East Basin and transferred to a hot cell for examination. Extensive testing planned for these elements will support the process design for the Integrated Process Strategy (IPS), with emphasis on drying and conditioning behavior. Visual examinations of the fuel elements confirmed that they are appropriate to meet testing objectives to provide design guidance for IPS processing parameters.
Date: March 6, 1997
Creator: Pitner, A.L. & Pyecha, T.D., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department
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Advanced reactors transition FY 1997 multi-year work plan WBS 7.3

Description: This document describes in detail the work to be accomplised in FY 1997 and the out-years for the Advanced Reactors Transition (WBS 7.3) under the management of the Babcock & Wilcox Hanford Company. This document also includes specific milestones and funding profiles. Based upon the Fiscal Year 1997 Multi-Year Work Plan, the Department of Energy will provide authorization to perform the work described.
Date: September 27, 1996
Creator: Hulvey, R.K.
Partner: UNT Libraries Government Documents Department
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Time delays between core power production and external detector response from Monte Carlo calculations

Description: One primary concern for design of safety systems for reactors is the time response of external detectors to changes in the core. This paper describes a way to estimate the time delay between the core power production and the external detector response using Monte Carlo calculations and suggests a technique to measure the time delay. The Monte Carlo code KENO-NR was used to determine the time delay between the core power production and the external detector response for a conceptual design of th… more
Date: August 1, 1996
Creator: Valentine, T. E. & Mihalczo, J. T.
Partner: UNT Libraries Government Documents Department
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Lessons Learned from Sandia National Laboratories' Operational Readiness Review of the Annular Core Research Reactor (ACRR)

Description: The Sandia ACRR (a Hazard Category 2 Nuclear Reactor Facility) was defueled in June 1997 to modify the reactor core and control system to produce medical radioisotopes for the Department of Energy (DOE) Isotope Production Program. The DOE determined that an Operational Readiness Review (ORR) was required to confirm readiness to begin operations within the revised safety basis. This paper addresses the ORR Process, lessons learned from the Sandia and DOE ORRS of the ACRR, and the use of the ORR … more
Date: May 17, 1999
Creator: Bendure, Albert O. & Bryson, James W.
Partner: UNT Libraries Government Documents Department
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Proposed Methodology for Establishing Area of Applicability

Description: This paper presents the application of sensitivity and uncertainty (S/U) analysis methodologies to the data validation tasks of a criticality safety computational study. The S/U methods presented are designed to provide a formal means of establishing the area (or range) of applicability for criticality safety data validation studies. The development of parameters that are analogous to the standard trending parameters form the key to the technique. These parameters are the so-called D parameters… more
Date: September 20, 1999
Creator: Broadhead, B. L.; Hopper, C. M. & Parks, C. V.
Partner: UNT Libraries Government Documents Department
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Pulsed reactor experiments at Oak Ridge

Description: This paper describes dynamic experiments for 3 pulsed reactors. 1st reactor was pulsed from some average power by rotating a partial Be reflector past an unreflected core face; the other 2 reactors were pulsed by rapid insertion of a fuel rod into the unmoderated and unreflected reactor at essentially zero neutron level with no significant neutron source present. The first reactor was a mockup of an EURATOM design (never constructed) of the proposed SORA Reactor, and the other two were the Heal… more
Date: December 31, 1994
Creator: Mihalczo, J.T.
Partner: UNT Libraries Government Documents Department
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Supplying the nuclear arsenal: Production reactor technology, management, and policy, 1942--1992

Description: This book focuses on the lineage of America`s production reactors, those three at Hanford and their descendants, the reactors behind America`s nuclear weapons. The work will take only occasional sideways glances at the collateral lines of descent, the reactor cousins designed for experimental purposes, ship propulsion, and electric power generation. Over the decades from 1942 through 1992, fourteen American production reactors made enough plutonium to fuel a formidable arsenal of more than twen… more
Date: January 1, 1994
Creator: Carlisle, R. P. & Zenzen, J. M.
Partner: UNT Libraries Government Documents Department
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High flux isotope reactor redesigned beryllium reflector thermal stress calculations

Description: The Beryllium reflector of the High Flux Isotope Reactor is currently redesigned for upgrading the capability of the reactor. The original design criteria are adopted in the redesign analysis. Both nuclear heating and thermal stress calculations are revised. The results show that more margin of safety have been achieved and the updated design assures more precise design estimates for the reflector thermal stress conditions. 1 ref., 2 figs., 2 tabs.
Date: June 1, 1996
Creator: Chang, S.J.
Partner: UNT Libraries Government Documents Department
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SCALE Graphical Developments for Improved Criticality Safety Aalyses

Description: New computer graphic developments at Oak Ridge National Ridge National Laboratory (ORNL) are being used to provide visualization of criticality safety models and calculational results as well as tools for criticality safety analysis input preparation. The purpose of this paper is to present the status of current development efforts to continue to enhance the SCALE (Standardized Computer Analyses for Licensing Evaluations) computer software system. Applications for criticality safety analysis in… more
Date: September 20, 1999
Creator: Barnett, D. L.; Bowman, S. M.; Horwedel, J. E. & Petrie, L. M.
Partner: UNT Libraries Government Documents Department
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Four in. three jaw type connector suitable for vertical mounting sample for job 11

Description: As authorized by purchase order No. 11-2532 dated March 11, 1949 of the Kellex Corp., the first sample of a 4 inch three jaw type connector for Job 11 was fabricated. The design of the connector was per Crane Co. drawing DR-25126-D except vertical mounting. The materials were per Crane Co. drawing A-24491-C. As instructed in verbal conversation with Dr. D.D. Jacobus and as requested in Mr. J.J. Cuniffe`s letter of May 6, 1949, and Ingersoll-Rand Company`s 1 1/4 inch 534 impact wrench with suita… more
Date: July 8, 1949
Creator: Grubbe, A.C.
Partner: UNT Libraries Government Documents Department
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The sharing of the Penn State Breazeale Reactor with other educational institutions

Description: The Penn State Radiation Science and Engineering Center (RSEC) integrates the Breazeale Reactor and its affiliated laboratories and facilities on the University Park Campus. Penn State has the only nuclear reactor in Pennsylvania dedicated to research and education. Its faculty have pioneered industrial and research applications of radiation and radioisotopes. In addition, the center and its affiliated faculty have access to the multidisciplinary resources and expertise available within Penn St… more
Date: December 31, 1995
Partner: UNT Libraries Government Documents Department
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Technical Safety Requirements for the Annular Core Research Reactor Faility (ACRRF)

Description: The Technical Safety Requirements (TSR) document is prepared and issued in compliance with DOE Order 5480.22, Technical Safety Requirements. The bases for the TSR are established in the ACRRF Safety Analysis Report issued in compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. The TSR identifies the operational conditions, boundaries, and administrative controls for the safe operation of the facility.
Date: September 1, 1998
Creator: Boldt, K. R.; McCrory, F. M.; Morris, F. M. & Talley, D. G.
Partner: UNT Libraries Government Documents Department
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