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Army Gas-Cooled Reactor Systems program: alternator final design report

Description: The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating. However, a large body of useful data was accumulated during the extensive development program. Of special interest are data on the rotor and stator design, the cooling requirements and on the distribution of eddy current losses. Analysis of the data indicates that a brushless alternator, only slightly larger and heavier than was specified for the ML-1, could be developed with a modest additional effort.
Date: June 1, 1964
Partner: UNT Libraries Government Documents Department

Technical evaluation of the proposed technical specification change for the Arkansas Nuclear Power Station, Unit 2

Description: This report documents the technical evaluation of the request for changes in the Technical Specifications for the Arkansas Nuclear Power Station, Unit 2. These changes were proposed by the licensee in a letter dated November 27, 1979. The basis for review included a report entitled Determination of Plant System Trip Setpoints Valves. The requested changes to the Technical Specifications were found to be acceptable based on information submitted by the licensee.
Date: August 1, 1980
Creator: Victor, R.A.
Partner: UNT Libraries Government Documents Department

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

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

Oconee 1, cycle 5 design report

Description: The Oconee 1, cycle 5 fuel cycle was designed to irradiate five fuel assemblies to a burnup of approximately 40,000 MWd/mtU. The fuel cycle design was performed using standard Babcock and Wilcox calculational techniques for nuclear fuel cycles. All applicable design criteria were satisfied. Valuable experimental data on the performance characteristics of high-burnup fuel assemblies will be obtained from these assemblies in subsequent post-irradiation examinations.
Date: May 1, 1979
Creator: Coleman, T.A. (ed.)
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

Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, January 1, 1979-March 31, 1979

Description: This report presents the results of work performed from January 1, 1979 through March 31, 1979 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. Work covered in this report includes the activities associated with the creep-rupture testing of the test materials for the purpose of verifying the stresses selected for the screening creep test program, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment.
Date: July 19, 1979
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

Empirical correlation of residual gamma radiation resulting from operation of the Health Physics Research Reactor

Description: An empirical equation has been developed which gives gamma dose equivalent rate as a function of time, distance, and fission yield after a pulsed operation of Oak Ridge National Laboratory's (ORNL) unshielded Health Physics Research Reactor (HPRR). A related expression which is applicable to steady-state reactor operation has been mathematically derived from the aforementioned empirical equation. The two relations can be used to predict the gamma dose equivalent rate to within 25% for times between 1 minute and 90 minutes after reactor shutdown. Similar agreement is expected for up to several days. In most cases the relations are expected to overestimate the gamma dose equivalent rate. 5 refs., 4 figs., 1 tab.
Date: April 1, 1985
Creator: Chou, T.L.; Ragan, G.E. & Sims, C.S.
Partner: UNT Libraries Government Documents Department

Eleventh ORNL personnel dosimetry intercomparison study, May 22-23, 1985

Description: The Eleventh Personnel Dosimetry Intercomparison Study was conducted at the Oak Ridge National Laboratory (ORNL) during May 22-23, 1985. Dosimeter badges from 44 participating organizations were mounted on Lucite block phantoms and exposed to four mixed-radiation fields with neutron dose equivalents around 5 mSv and gamma dose equivalents between 0.1 and 0.7 mSv. Results of this study indicated that no participants had difficulty obtaining measurable indication of neutron exposure at the provided dose equivalent levels, and very few had difficulty obtaining indication of gamma exposure at dose equivalents as low as 0.10 mSv. Average neutron results for all dosimeter types were within 20% of reference values with no obvious spectrum dependence. Different dosimeter types (albedo, direct interaction TLD, film, recoil track, and combination albedo-track) with 10 or more reported measurements provided average results within 35% of reference values for all spectra. With regard to precision, about 80% of the reported neutron results had single standard deviations within 10% at the means which indicates that precision is not a problem relative to accuracy for most participants. Average gamma results were greater than reference values by factors of 1.07 to 1.52 for the four exposures with TLD systems being more accurate than film. About 80% of all neutron results and 67% of all gamma results met regulatory standards for measurement accuracy and approximately 70% of all neutron data satisfied national dosimetry accreditation criteria for accuracy plus precision. In general, neutron dosimeter performance observed in this intercomparison was much improved compared to that observed in the prior studies while gamma dosimeter performance was about the same.
Date: July 1, 1986
Creator: Swaja, R.E.; Oyan, R. & Sims, C.S.
Partner: UNT Libraries Government Documents Department

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2

Description: This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity.
Date: May 1, 1986
Creator: Doerge, D.H.; Miller, R.L. & Scotti, K.S.
Partner: UNT Libraries Government Documents Department

Post-irradiation examination of Oconee 1 fuel: cycle 1 nondestructive test phase

Description: Standard B and W pressurized water reactor fuel was examined after one cycle of irradiation in the Oconee 1 reactor. The examination was conducted in the Oconee Units 1 and 2 spent fuel storage pool using underwater test equipment. Data obtained included spring constants, rod and assembly dimensional changes, crud analysis, and fuel column axial gap and stack lengths. Parametric changes generally were well within the design envelope. The 36 assemblies that were visually examined were structurally sound and showed no evidence of cocked grids, fretting, or visually observable rod bowing. The only exception was two isolated cases of rod defects.
Date: June 1, 1979
Partner: UNT Libraries Government Documents Department

Potential seismic structural failure modes associated with the Zion Nuclear Plant. Seismic safety margins research program (Phase I). Project VI. Fragilities

Description: The Zion 1 and 2 Nuclear Power Plant consists of a number of structures. The most important of these from the viewpoint of safety are the containment buildings, the auxiliary building, the turbine building, and the crib house (or intake structure). The evaluation of the potential seismic failure modes and determination of the ultimate seismic capacity of the structures is a complex undertaking which will require a large number of detailed calculations. As the first step in this evaluation, a number of potential modes of structural failure have been determined and are discussed. The report is principally directed towards seismically induced failure of structures. To some extent, modes involving soil foundation failures are discussed in so far as they affect the buildings. However, failure modes involving soil liquefaction, surface faulting, tsunamis, etc., are considered outside the scope of this evaluation.
Date: October 1, 1979
Partner: UNT Libraries Government Documents Department

Technical study for the chemical cleaning of Dresden-1 DNS-D1-016. Volume VII. Appendices IX thru XIV

Description: Appendices are presented which contain information concerning the decontamination of Dresden-1; consultant's opinions; proceedings of the American Power Conference, Volume 37, 1975; health physics reports; toxicological properties and industrial handling hazards of Dow solvent NS-1; and expected radiation dose rates in the new Dresden station radioactive waste processing building.
Date: June 15, 1977
Partner: UNT Libraries Government Documents Department

Shippingport Atomic Power Station (PWR). Technical progress report, July 26, 1979-January 25, 1980

Description: The Shippingport Atomic Power Station was operated with the Light Water Breeder Reactor core at high power levels (base load) throughout this report period except for reductions in power or brief shutdowns to perform planned testing. Evaluation of core test data taken during this period continues to show that the core is operating in accordance with design predictions. Periodic flow coefficient of reactivity measurements is reported which all meet the criteria on which the revised core protection setpoints and station operating procedures were based.
Date: January 1, 1980
Partner: UNT Libraries Government Documents Department