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Summary data for U. S. commercial nuclear power plants in the United States

Description: A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables.
Date: March 20, 1978
Creator: Heddleson, F.A.
Partner: UNT Libraries Government Documents Department
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Cycle 7 outage experience. [Fast Flux Test Facility (FFTF)]

Description: The scheduled 58-day refueling outage in preparation for the seventh operating cycle of the Fast Flux Test Facility (FFTF) was successfully completed three days ahead of schedule. The planning and execution of the outage was greatly aided by Project/2 automated scheduling capabilities. For example, the use of ''maintenance windows'' and resource loading capabilities was particularly effective. The value of the planning process was demonstrated by the smooth transition into the outage phase afte… more
Date: March 1, 1986
Creator: Gadeken, A.D.
Partner: UNT Libraries Government Documents Department
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Licensee Event Report (LER) compilation for month of February 1984. Vol. 3, No. 2

Description: This monthly report contains LER operational information that was processed into the LER data file of the Nuclear Safety Information Center (NSIC) during this period. The LER summaries are arranged alphabetically by facility name and then chronologically by event date for each facility. Component, system, keyword, and component vendor indexes follow the summaries.
Date: March 1, 1984
Partner: UNT Libraries Government Documents Department
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Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

Description: This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for… more
Date: March 1, 1982
Creator: McCormack, K.E. & Gallaher, R.B.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor. Quarterly report, October--December 1977

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled cycle interruption shutdown resulted in an on-stream time of 90.3 percent. A new inner control cylinder and a set of outer control plates with remotely replaced bearing brackets were installed. The semiannual core component inspection was made.
Date: March 1, 1978
Creator: Corbett, B. L.; McCord, R. V. & Poteet, K. H.
Partner: UNT Libraries Government Documents Department
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Comparison of the radiological impacts of thorium and uranium nuclear fuel cycles

Description: This report compares the radiological impacts of a fuel cycle in which only uranium is recycled, as presented in the Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors (GESMO), with those of the light-water breeder reactor (LWBR) thorium/uranium fuel cycle in the Final Environmental Statement, Light Water Breeder Reactor Program. The significant offsite radiological impacts from routine operation of the fuel cycles result fro… more
Date: March 1, 1982
Creator: Meyer, H. R.; Witherspoon, J. P.; McBride, J. P. & Frederick, E. J.
Partner: UNT Libraries Government Documents Department
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Review of the Oconee-3 probabilistic risk assessment: external events, core damage frequency. Volume 2

Description: A review of the Oconee-3 Probabilistic Risk Assessment (OPRA) was conducted with the broad objective of evaluating qualitatively and quantitatively (as much as possible) the OPRA assessment of the important sequences that are ''externally'' generated and lead to core damage. The review included a technical assessment of the assumptions and methods used in the OPRA within its stated objective and with the limited information available. Within this scope, BNL performed a detailed reevaluation of … more
Date: March 1, 1986
Creator: Hanan, N. A.; Ilberg, D.; Xue, D.; Youngblood, R.; Reed, J. W.; McCann, M. et al.
Partner: UNT Libraries Government Documents Department
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A process for risk-focused maintenance

Description: This report presents a process for focusing maintenance resources on components that enable nuclear plant systems to perform their essential functions and on components whose failure may initiate challenges to safety systems, so as to have the greatest impact in decreasing risk. The process provides criteria, based on risk, for deciding which components are critical to risk and determining what maintenance activities are required to ensure reliable operation of those risk-critical components. T… more
Date: March 1, 1991
Creator: Lofgren, E. V.; Cooper, S. E.; Kurth, R. E. & Phillips, L. B. (Science Applications International Corp., McLean, VA (USA))
Partner: UNT Libraries Government Documents Department
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Main-coolant-pump shaft-seal guidelines. Volume 2. Operational guidelines. Final report. [PWR; BWR]

Description: This report presents a set of guidelines and criteria for improving main coolant pump shaft seal operational reliability. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies. Usage procedures/practices and operational environment influence on seal life and reliability from the most recent such survey are summarized. The shaft seal and its auxiliary supporting systems are discussed both from technical and operational related viewpoints.
Date: March 1, 1983
Creator: Fair, C.E. & Greer, A.O.
Partner: UNT Libraries Government Documents Department
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A history of major Hanford facilities and processes involving radioactive material. [Contains glossary]

Description: The Hanford Environmental Dose Reconstruction (HEDR) Project was established in 1987 to estimate radiation doses that people could have received from nuclear operations at the Hanford Site since 1944. Hanford Site operations began in 1944 to produce plutonium for nuclear weapons. This effort included fabricating fuel elements, irradiating the fuel in nuclear reactors, and separating the resulting plutonium from uranium and fission byproducts. To build a foundation for the first step in estimati… more
Date: March 1, 1991
Creator: Ballinger, M.Y. & Hall, R.B.
Partner: UNT Libraries Government Documents Department
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Design guide for category V reactors transient reactors

Description: The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requ… more
Date: March 1, 1979
Creator: Brynda, W J; Karol, R C; Lobner, P R; Powell, R W & Straker, E A
Partner: UNT Libraries Government Documents Department
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Fast Shutdown System tests in the Georgia Tech Research Reactor

Description: The Fast Shutdown System (FSS) is a new safety system design concept being considered for in installation in the Savannah River (SRS) production reactors. This system is expected to mitigate the consequences of a Design Basis Loss of Coolant Accident, and therefore allow higher operational power levels. A test of this system in the Georgia Tech Research Reactor is proposed to demonstrate the efficacy of this concept. Three tests will be conducted at full power (5MW) and one at low power (100kw)… more
Date: March 16, 1990
Creator: Wallace, J.M.
Partner: UNT Libraries Government Documents Department
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Piping vibrations measured during FFTF startup

Description: An extensive vibration survey was conducted on the Fast Flux Test Facility piping during the plant acceptance test program. The purpose was to verify that both mechanical and flow induced vibration amplitudes were of sufficiently low level so that pipe and pipe support integrity would not be compromised over the plant design lifetime. Excitation sources included main heat transport sodium pumps, reciprocating auxiliary system pumps, EM pumps, and flow oscillations. Pipe sizes varied from one-in… more
Date: March 1, 1981
Creator: Anderson, M. J.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: February 1963

Description: This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: March 14, 1963
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
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Review of stuck slugs

Description: Records show that difficulty has been encountered with the discharge of two tubes in B Pile, twelve in the D Pile, and fifteen in the F Pile during the period from initial start-up until March 15, 1948. In sixteen cases the tubes have been replaced, six of the tubes which were in the fringe have been made air tubes, four did not warrant replacement, and three are to be replaced in the future. General statistics for these twenty-nine tubes are presented with additional details in this report.
Date: March 15, 1948
Creator: Alexander, W. K. & Woods, W. K.
Partner: UNT Libraries Government Documents Department
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Reactivity and efficiency trends vs operating trends for B, D, DR, and F reactors, 1956--1960

Description: Changes in operation and corresponding changes in the reactivity status of Hanford reactors are the result of a continuing effort to improve operating efficiency. Trends data related to these changes in operation and reactivity have been published previously for the periods from 1955 through 1959. The purpose of this report is to include trends data for 1960. Bar graphs in the first part of the report show yearly averages of selected data, and the line graphs in the second part show the interre… more
Date: March 1, 1962
Creator: Perl, E. R.
Partner: UNT Libraries Government Documents Department
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Hanford Works Monthly Report: February 1953

Description: This document presents a summary of work and progress at the Hanford Engineer Works for February 1953. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sectio… more
Date: March 18, 1953
Partner: UNT Libraries Government Documents Department
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Summary of KER-1 operation, February 15, 1958--March 1, 1960

Description: Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.
Date: March 3, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Fast Shutdown System tests in the Georgia Tech Research Reactor

Description: The Fast Shutdown System (FSS) is a new safety system design concept being considered for in installation in the Savannah River (SRS) production reactors. This system is expected to mitigate the consequences of a Design Basis Loss of Coolant Accident, and therefore allow higher operational power levels. A test of this system in the Georgia Tech Research Reactor is proposed to demonstrate the efficacy of this concept. Three tests will be conducted at full power (5MW) and one at low power (100kw)… more
Date: March 16, 1990
Creator: Wallace, J. M.
Partner: UNT Libraries Government Documents Department
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Advantages of palmolive alternate

Description: It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date: March 17, 1959
Creator: Coppinger, E. A. & Merrill, E. T.
Partner: UNT Libraries Government Documents Department
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Hanford Works monthly report, February 1951

Description: This is a progress report of the production on the Hanford Reservation for the month of February 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.
Date: March 20, 1951
Creator: Prout, G. R.
Partner: UNT Libraries Government Documents Department
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