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Westinghouse independent safety review of Savannah River production reactors

Description: Westinghouse Electric Corporation has performed a safety assessment of the Savannah River production reactors (K,L, and P) as requested by the US Department of Energy. This assessment was performed between November 1, 1988, and April 1, 1989, under the transition contract for the Westinghouse Savannah River Company's preparations to succeed E.I. du Pont de Nemours Company as the US Department of Energy contractor for the Savannah River Project. The reviewers were drawn from several Westinghouse… more
Date: April 1, 1989
Creator: Leggett, W. D.; McShane, W. J. (Westinghouse Hanford Co., Richland, WA (USA)); Liparulo, N. J.; McAdoo, J. D.; Strawbridge, L. E. (Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear and Advanced Technology Div.); Toto, G. (Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Services Div.) et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Seismic hazard evaluation for the high-flux isotope reactor (HFIR) Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: This study investigates the probabilistic hazard of earthquake-induced ground shaking at the HFIR facility, Oak Ridge, Tennessee. These results will be used to calculate plant response and potential effects in a Probabilistic Risk Assessment (PRA). For this purpose, several guidelines apply to this work. First, both the frequency of exceedance and the uncertainty in frequency of exceedance of various ground motion levels must be represented. These are required by the PRA so that the frequency a… more
Date: September 1, 1991
Creator: McGuire, R.K. & Toro, G.R. (Risk Engineering, Inc., Golden, CO (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Iodine-123 generator/iodination kit: a preliminary report

Description: Preliminary results are described of a xenon-123 filled device to serve as a combination iodine-123 generator/iodination kit. Xenon-123 is produced in the Brookhaven Linac Isotope Producer (BLIP) by the reaction /sup 127/I(p, 5n)/sup 123/Xe. The device consists of a small glass ampoule containing an internal glass breakseal and a flanged neck on which is crimped a multi-injection type septum. The ampoule contains a hydrogen sulfide atmosphere to assure that the iodine generated from the decay o… more
Date: January 1, 1980
Creator: Richards, P; Prach, T; Srivastava, S C & Meinken, G E
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dedicated medical ion accelerator design study. Final report

Description: Results and conclusions are reported from a design study for a dedicated medical accelerator. Basing efforts on the current consensus regarding medical requirements, the resulting demands on accelerator and beam delivery systems were analyzed, and existing accelerator technology was reviewed to evaluate the feasibility of meeting these demands. This general analysis was augmented and verified by preparing detailed preliminary designs for sources of therapeutic beams of neutrons, protons and hea… more
Date: December 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation of curium-americium oxide microspheres by resin-bead loading

Description: Resin-bead loading and calcination techniques have been used to produce all curium and americium oxide feed material (about 2.2 kg) for HFIR targets since 1971. The process based on Dowex 50W resin has progressed from a series of test runs, through special production runs, into routine production in permanent equipment beginning in 1975. Key attributes of this process are its reliability, high yields, and ease of operation. The process is suited for remote operation in hot cells. Yields approac… more
Date: January 1, 1980
Creator: Chattin, F. R.; Benker, D. E.; Lloyd, M. H.; Orr, P. B.; Ross, R. G. & Wiggins, J. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Optimum collection time for short-lived isotopes

Description: In dealing with an isotope whose half-life is comparable to the processing time, the target-maker wishes to terminate the procedure at a point that will maximize the amount of the desired material on the target. This cut-off time is not always easy to determine; while it is true that fresh material is constantly being deposited, the isotope previously laid down is steadily decaying, and in addition the rate at which fresh material is applied is usually decreasing. The purpose of this paper is t… more
Date: January 1, 1977
Creator: Lerner, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Feynmann variance-to-mean method

Description: The Feynmann and other fluctuation techniques have been shown to be useful for determining the multiplication of subcritical systems. The moments of the counting distribution from neutron detectors is analyzed to yield the multiplication value. We present the methodology and some selected applications and results and comparisons with Monte Carlo calculations.
Date: January 1, 1985
Creator: Dowdy, E. J.; Hansen, G. E. & Robba, A. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cyclotrons for clinical and biomedical research with PET

Description: The purpose of this commentary is to present some background material on cyclotrons and other particle accelerators particularly with a view toward the considerations behind acquiring and installing such a machine for purely clinical and/or biomedical research use.
Date: January 1, 1987
Creator: Wolf, A.P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Mound Facility activities in chemical and physical research: July-December 1979

Description: Research is reported in the following fields: isotope separation (Ar, C, He, Kr, Ne, O, Xe), low-temperature research (H intermolecular potential functions, gas analysis in trennschaukel), separation chemistry (/sup 229/Th, /sup 231/Pa, /sup 230/Th, /sup 234/U), separation research (liquid thermal diffusion, Ca isotope separation, molecular beam scattering, mutual diffusion of noble gas mixtures, lithium chemical exchange with cryptands), and calculations in plutonium chemistry (algorithms, val… more
Date: June 18, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor. Quarterly report, October, November, and December 1979

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled midcycle shutdown resulted in an on-stream time of 93.6% for the quarter. This gave the HFIR an on-stream time for the year of 91.3%. The outer control plates were replaced, and the annual core components inspection was made.
Date: August 1, 1980
Creator: Corbett, B.L. & Poteet, K.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide production in /sup 136/Xe bombardments of /sup 249/Cf

Description: The production cross sections for the actinide products from /sup 136/Xe bombardments of /sup 249/Cf at energies 1.02, 1.09, and 1.16 times the Coulomb barrier were determined. Fractions of the individual actinide elements were chemically separated from recoil catcher foils. The production cross sections of the actinide products were determined by measuring the radiations emitted from the nuclides within the chemical fractions. The chemical separation techniques used in this work are described … more
Date: August 1, 1985
Creator: Gregorich, K.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gamma densitometer for measuring Pu density in fuel tubes

Description: A fuel-gamma-densitometer (FGD) has been developed to examine nondestructively the uniformity of plutonium in aluminum-clad fuel tubes at the Savannah River Plant (SRP). The monitoring technique is ..gamma..-ray spectroscopy with a lead-collimated Ge(Li) detector. Plutonium density is correlated with the measured intensity of the 208 keV ..gamma..-ray from /sup 237/U (7d) of the /sup 241/Pu (15y) decay chain. The FGD measures the plutonium density within 0.125- or 0.25-inch-diameter areas of th… more
Date: January 1, 1982
Creator: Winn, Willard G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Force analysis of the advanced neutron source control rod drive latch mechanism

Description: The Advanced Neutron Source reactor (ANS), a proposed Department of Energy research reactor currently undergoing conceptual design at the Oak Ridge National Laboratory (ORNL), will generate a thermal neutron flux approximating 10{sup 30} M{sup {minus}2}{emdash}S{sup {minus}1}. The compact core necessary to produce this flux provides little space for the shim safety control rods, which are located in the central annulus of the core. Without proper control rod drive design, the control rod drive … more
Date: January 1, 1989
Creator: Damiano, B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design data and safety features of commercial nuclear power plants. Vol. I. Docket No. 50-3 through 50-295

Description: BS>Design data, safety features, and site characteristics are summarized for thirty-two commercial nuclear power plants in the United States. Six pages of data are presented for each plant consisting of Thermal-Hydraulic and Nuclear Factors, Containment Features, Emergency Core Cooling Systems, Site Features, Circulating Water System Data, and Miscellaneous Factors. An aerial perspective is also presented for each plant. Those covered in this volume are Indian Point No. 1, Docket Number 50-3… more
Date: December 1, 1973
Creator: Heddleson, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Automatic diagnosis of alarms: a system to improve operator emergency response

Description: A system is being developed at the Savannah River Plant to help reactor operators respond to multiple alarms in a developing incident situation. The need for such systems has becme evident in recent years, particularly after the Three Mile Island incident.
Date: January 1, 1980
Creator: Olson, H. P.; Gimmy, K. L.; Nomm, E. & Finley, R. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of macroreticular anion exchange resin - RTA-893-R

Description: The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a c… more
Date: June 7, 1965
Creator: Baumann, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High flux isotope reactor quarterly report, July, August, and September of 1981

Description: Routine reactor operation with four end-of-cycle shutdowns and two unscheduled shutdowns resulted in an on-stream time of 91.3% for the quarter. The outer control plates and the inner control cylinder were changed and a semi-annual core component inspection was made.
Date: April 1, 1982
Creator: Corbett, B. L. & Poteet, K. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Historical overview of domestic spent fuel shipments: Update

Description: This report presents available historic data on most commercial and research reactor spent fuel shipments in the United States from 1964 through 1989. Data include sources of the spent fuel shipped, types of shipping casks used, number of fuel assemblies shipped, and number of shipments made. This report also addresses the shipment of spent research reactor fuel. These shipments have not been documented as well as commercial power reactor spent fuel shipment activity. Available data indicate th… more
Date: July 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MHTGR: New production reactor summary of experience base

Description: Worldwide interest in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) stems from the capability of the system to retain the advanced fuel and thermal performance while providing unparalleled levels of safety. The small power level of the MHTGR and its passive systems give it a margin of safety not attained by other concepts being developed for power generation. This report covers the experience base for the key nuclear system, components, and processes related to the MHTGR-NPR. 9 refs.,… more
Date: March 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of ANS-5. 1 as the decay heat standard at the Savannah River Plant

Description: The Savannah River Laboratory (SRL) is upgrading the methods used to predict the post shutdown decay heat of the Savannah River reactors by implementing procedures based on the ANS Decay Heat Power in Light Water Reactors standard. This approach takes advantage of the large volume of research used in developing the standard and establishes compatibility with the nuclear industry. To qualify the decay heat standard for use, a series of comparisons were made between detailed decay heat calculatio… more
Date: January 1, 1982
Creator: Apperson, Jr, C. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparison of eigenvalue computations for the Savannah River K Reactor using 5 and 7 digit dimensional and isotopic quantities

Description: A study was undertaken to characterize the reactivity temperature coefficient (RTC) behavior for the Savannah River K-Reactor pursuant to the safety review mandated by the Department of Energy (DOE) in August 1988. During the course of the investigation, it was found that the accuracy levels required in dimensional and isotopic quantities at elevated temperatures were much greater than was initially supposed and are typically used in reactor neutronics calculations. The codes involved do not au… more
Date: January 1, 1991
Creator: Durkee, J.W. Jr.; Mosteller, R.D.; Perry, R.T. & Sapir, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of water chemistry on the erosion-corrosion of aluminum in high temperature high velocity water

Description: This paper reports on a laboratory study of erosion-corrosion on aluminum surfaces in high temperature water. It is essentially a continuation of a similar previous study with refinement in testing procedure and the addition of electrochemical measurements to study the phenomenon. The electrochemical procedures are of intrinsic worth, because such measurements have never before been conducted with such an unusual cell geometry as imposed by the erosion-corrosion testing apparatus.
Date: January 30, 1970
Creator: Jones, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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