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Oak Ridge Research Reactor quarterly report, July, August, and September of 1977

Description: The ORR operated at an average power level of 29.5 MW for 23.4% of the time during July, August, and September of 1977. Three fuel elements were declared spent (60.7% burnup) during the quarter, while five new elements were placed in service. The reactor was shut down on seven occasions, none of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was quite low, with the reactor remaining available for operation 86.5% of the time. Maintenance activities, both mechanical and instrument were essentially routine in nature. In-service inspections completed during the quarter included inspection of the ORR primary heat exchanger No. 2.
Date: January 1, 1978
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

Los Alamos Omega West Reactor

Description: A description is given of the Omega West Reactor and associated experimental facilities, followed by a brief discussion of recent usage, new experiments, and future prospects.
Date: January 1, 1983
Creator: Lyle, A.R.; Williams, H.T. & Bunker, M.E.
Partner: UNT Libraries Government Documents Department

Oak Ridge research reactor. Quarterly report, April-June 1979

Description: The ORR operated at an average power level of 29.9 MW for 77.9% of the time during April, May, and June of 1979. The reactor was shut down on seven occasions, two of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was normal, with the reactor remaining available for operation 86.5% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature.
Date: December 1, 1979
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge Research Reactor quarterly report October, November and December of 1978

Description: The ORR operated at an average power level of 29.0 MW for 80.9% of the time during October, November, and December of 1978. The reactor was shut down on fourteen occasions, four of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was normal, with the reactor remaining available for operation 92.2% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature.
Date: May 1, 1979
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge Research Reactor quarterly report, January-March, 1979

Description: The ORR operated at an average power level of 28.9 MW for 84.2% of the time during January, February and March of 1979. The reactor was shut down on seventeen occasions, three of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was normal, with the reactor remaining available for operation 93.6% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature with the exception of one mechanical design change. Special tests or measurements completed during the quarter included: (1) preliminary measurements for the LWR Pressure Vessel Irradiation Program; (2) flux mapping for Core No. 148-A; and (3) calibration of all six shim rods.
Date: October 1, 1979
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

LOFT DTT rake pin stress analysis

Description: A stress analysis of the 3/8-inch and 1/4-inch pins which hold the rake assembly to the flange was performed and shows stresses to be lower than the Class 1 allowables of the ASME Boiler and Pressure Vessel Code. The alternating pin stresses were found to be below the endurance limit and fatigue failure will not occur. The rake assembly was assumed to be loaded by steady drag and lift forces and alternating vortex shedding forces.
Date: January 23, 1979
Creator: Mosby, W.R.
Partner: UNT Libraries Government Documents Department

Loft fire protection

Description: Quantified criteria that was developed and applied to provide in-depth fire protection for the Loss of Fluid Test (LOFT) Facility are presented. The presentation describes the evolution process that elevated the facility's fire protection from minimal to that required for a highly protected risk or improved risk. Explored are some infrequently used fire protection measures that are poorly understood outside the fire protection profession.
Date: January 1, 1980
Creator: White, E.R. & Jensen, J.D.
Partner: UNT Libraries Government Documents Department

Justification for 80 PSI railroad door sealing pressure

Description: The normal operating pressure for the inner and outer Railroad Door Seals is 90 psig. The instrumentation which monitors this pressure does not provide assurance that the 90 psig can be maintained during reactor operations. A decrease in pressure is detected by a low level pressure alarm set to alarm at 88 psig. When another 8 psig is allowed for the instrument error of this alarm and the operating band during the leak test, the minimum pressure maintained in the seals is reduced to 80 psig. 80 psig, therefore, is the pressure that the LOFT Technical Specifications have committed to maintain.
Date: December 20, 1977
Creator: Larson, R.H.
Partner: UNT Libraries Government Documents Department

LOFT facility and test program

Description: The Loss-of-Fluid Test (LOFT) test facility, program objectives, and the experiments planned are described. The LOFT facility is related to the smaller Semiscale facility and the larger commercial pressurized water reactors. The fact that LOFT is a computer model assessment tool rather than a demonstration test is emphasized. Various types of reactor safety experiments planned through 1983 are presented.
Date: November 1, 1979
Creator: McPherson, G.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge Research Reactor quarterly report, April, May, and June 1981

Description: The ORR operated at an average power level of 29.8 MW for 90.7% of the time during April, May, and June 1981. The reactor was shut down on eight occasions, one of which was unscheduled. Reactor downtime needed for refueling, maintenance, and checks was normal, with the reactor remaining available for operation 91.6% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature. In-service inspection completed during the quarter is described.
Date: January 1, 1982
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge research reactor. Quarterly report, January, February, and March 1981

Description: The ORR operated at an average power level of 27.9 MW for 88.9% of the time during January, February, and March of 1981. The reactor was shut down on seventeen occasions, seven of which were unscheduled. Reactor downtime needed for refueling, maintenance, and checks was normal, with the reactor remaining available for use 92.6% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature with the exception of one Reactor Instrumentation and Controls Design Change Memo and one Mechanical Design Change Memo. Special tests or measurements completed during this quarter are reported in a summary entitled, ORR Reactivity and Flux Comparisons between a 280 g, 45 Weight Percent Enriched Texas Instrument Fuel Element and a 265 g Standard 93 Weight Percent Enriched Texas Instrument Fuel Element.
Date: January 1, 1982
Creator: Hurt, III, S. S. & Lance, E. D.
Partner: UNT Libraries Government Documents Department

Design and performance of the drag-disc turbine transducer

Description: Mass flow rates at the Loss-of-Fluid Test (LOFT) facility, EG and G Idaho, Inc., at the Idaho National Engineering Laboratory, are measured with the drag-disc turbine transducer (DTT). Operational description of the DTT and the developmental effort are discussed. Performance data and experiences with this transducer have been evaluated and are presented in this paper.
Date: January 1, 1979
Creator: Averill, R.H.; Goodrich, L.D. & Ford, R.E.
Partner: UNT Libraries Government Documents Department

450/sup 0/F step transient thermal analysis of the LOFT pressurizer surge and spray line piping

Description: The LOFT pressurizer spray and surge line piping was analyzed for a 450/sup 0/F step change in fluid temperature. This transient was chosen to conservatively represent several pressurizer operating transients that had not previously been analyzed. These include temperature transients resulting from a 300/sup 0/F ..delta..T between pressurizer temperature and cold leg temperature, injection of a cooled (70/sup 0/F) slug of stagnant fluid into the hot (540/sup 0/F) spray line piping, and inflow of 100/sup 0/F primary coolant system water into the hot (480/sup 0/F) surge line piping.
Date: July 7, 1977
Creator: Tolan, B.J.
Partner: UNT Libraries Government Documents Department

Loft waste gas processing system analysis. Line 1-1/2''-BSV-10-VD outside penetration S-5C

Description: Lines 1''-BSV-10-VD and 1/sup 1///sub 2/''-BSV-10-VD were analyzed to ASME Section III, Subsection NC (Class 2) criteria. The lines are part of the Waste Gas Processing System. The model considered the portion of the lines outside the containment. The analysis showed that Class 2 requirements will be met with the pipe supports specified in this report.
Date: August 16, 1978
Creator: Pierce, A.T.
Partner: UNT Libraries Government Documents Department

Data acquisition and control system for the K/sub 1C/-HSST experiments at the ORR

Description: Major components and primary functions of the process control system for the K/sub 1C/-HSST irradiation experiments at the Oak Ridge Research (ORR) are described. Information relative to methodology for integrating unique features of the Digital Equipment Corporation's RSX-11M Operating System with analog-to-digital and digital-to-analog hardware is presented. In particular, data flow among various real-time applications programs relative to system hardware is presented. General features of the temperature control algorithm are presented, and results that illustrate the spatial temperature distribution in the capsule achieved by the control system are included.
Date: January 1, 1984
Creator: Miller, L.F. & Hobbs, R.W.
Partner: UNT Libraries Government Documents Department

Oak Ridge Research Reactor quarterly report, April, May, and June of 1978

Description: The ORR operated at an average power level of 27.8 MW for 72.6% of the time during April, May, and June of 1978. The reactor was shut down on fifteen occasions, two of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was higher than normal due to beam-hole-plug maintenance, with the reactor remaining available for operation 82.4% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature. Special tests or measurements completed during the quarter included gamma flux (heating) measurements made in core positions E-7, E-5, E-3, and C-7 using lattice configurations as indicated in figure Nos. 5, 6, 7, 8, 9, and 10.
Date: December 1, 1978
Creator: Hurt, III, S. S. & Lance, E. D.
Partner: UNT Libraries Government Documents Department

Oak Ridge research reactor quarterly report, January, February, and March of 1980

Description: The ORR operated at an average power level of 29.9 MW for 91.3% of the time during January, February, and March of 1980. The reactor was shut down on twelve occasions, six of which were unscheduled. Reactor downtime needed for refueling, maintenance and checks was normal, with the reactor remaining available for use 93.7% of the time. Maintenance activities, both mechanical and instrument, were essentially routine in nature with the exception of one Reactor Instrument and Controls Design Change Memo.
Date: October 1, 1980
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

Oak Ridge Research Reactor quarterly report, January, February, and March of 1978

Description: The ORR operated at an average power level of 28.7 MW for 73.4 percent of the time during January, February, and March of 1978. Eight new fuel elements were placed in service. The reactor was shut down on sixteen occasions, one of which was unscheduled. Reactor downtime needed for refueling, maintenance and checks was quite low, with the reactor remaining available for operation 88.9 percent of the time. Maintenance activities, both mechanical and instrument were essentially routine in nature. Special tests or measurements completed during the quarter included: (1) reactivity measurement of the Metals and Ceramics Division's (ORR-MFE-1) experiment in CP-C7; (2) flux mapping for core No. 143-B; and (3) calibration of all six shim rods on February 12, 1978 (Appendix A), and calibration of shim rods Nos. 2 through 6 on February 16, 1978.
Date: July 1, 1978
Creator: Hurt, S.S. III & Lance, E.D.
Partner: UNT Libraries Government Documents Department

LOFT contribution to PWR fuel analysis and testing

Description: The paper provides a brief overview of the Loss-of-Fluid Test (LOFT) Facility, a review of the key results from LOCA tests performed to date, and plans for the future of LOFT, as an introduction to the more specific information about LOFT fuel that is to follow. The purpose of the LOFT tests is to provide data for assessing the accuracy of the analytical models used in evaluating the safety of commercial nuclear power plants. While the main purpose of LOFT is to investigate phenomena important to the loss-of-coolant accident (LOCA), the 55 MWt LOFT reactor system has been scaled to commercial power reactors and heavily instrumented so that information on fuel and system behavior over a range of normal and off-normal conditions can be obtained.
Date: January 1, 1978
Creator: Leach, L.P.
Partner: UNT Libraries Government Documents Department

Computerized process control system for the ORR-PSF irradiation experiment. Part 2: mathematical basis and computer implementation of the temperature control algorithm. Volume 2

Description: A brief description of the Oak Ridge Reactor Pool Side Facility (ORR-PSF) and of the associated control system is given. The ORR-PSF capsule temperatures are controlled by a digital computer which regulates the percent power delivered to electrical heaters. The total electrical power which can be input to a particular heater is determined by the setting of an associated variac. This report concentrates on the description of the ORR-PSF irradiation experiment computer control algorithm. The algorithm is an implementation of a discrete-time, state variable, optimal control approach. The Riccati equation is solved for a discretized system model to determine the control law. Experiments performed to obtain system model parameters are described. Results of performance evaluation experiments are also presented. The control algorithm maintains both capsule temperatures within a 288/sup 0/C +-10/sup 0/C band as required. The pressure vessel capsule temperatures are effectively maintained within a 288/sup 0/C +-5/sup 0/C band.
Date: November 1, 1980
Creator: Miller, L.F.
Partner: UNT Libraries Government Documents Department

Calculations of the startup experiments at the Poolside Facility

Description: Discrete ordinate calculations are made and the results compared with measurements performed in the startup experiment at the Poolside Facility. Because of the physical size of the simulated surveillance capsule used in this experiment, the analytic procedure is more complicated than one adopted in earlier calculations of the PCA-PVF and PSF. The comparisons indicate the pressure vessel fluences in the long-term irradiation experiments still presently going on at the PSF, and which are geometrically identical to the startup experiment, can only be predicted to within about 20%.
Date: January 1, 1982
Creator: Williams, M.L. & Maerker, R.E.
Partner: UNT Libraries Government Documents Department

Calibration of a drag disc turbine transducer and a gamma beam densitometer to measure the mass flow rate in separated horizontal two-phase flow

Description: The accurate measurement of two-phase mass flow rate is very important in experiments, such as the LOFT experiment, which investigate the hypothetical Loss-of-Coolant Accident (LOCA). This paper analyzes experiments designed to determine the behavior of a LOFT free field drag disc turbine transducer (DTT) and a LOFT-type three-beam gamma densitometer in a steady state, horizontal high pressure steam-water flow. The experiments were conducted in a mass flow and void fraction range where a variety of separated flow regimes existed which strongly influenced the performance of the DTT. It is shown that the accuracy of the instruments is mainly a function of the void fraction.
Date: January 1, 1979
Creator: Reimann, J. & Solbrig, C.W.
Partner: UNT Libraries Government Documents Department

High Flux Isotope Reactor. Quarterly report, July--September 1977

Description: Routine reactor operation with three end-of-cycle shutdowns and the completion of a fourth carried over from the previous quarter resulted in an on-stream time of 95.5 percent. The control plates were changed, and a new inner control cylinder was installed. Basic operating data for the quarter are listed.
Date: December 1, 1977
Creator: Corbett, B.L.; McCord, R.V. & Poteet, K.H.
Partner: UNT Libraries Government Documents Department