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The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling

Description: Abstract: "The critical mass both of an untamped and water-tamped sphere with parabolic radial variation of the intrinsic buckling is calculated by a perturbation method. The result is applied to finding the minimum critical mass of plutonium in water suspension with infinite water temper; the calculations show that the minimum critical mass at constant concentration may be reduced by an amount of the order of 7.6% when the concentration of plutonium is permitted to vary throughout the suspension."
Date: April 28, 1949
Creator: Muller, G. M.
Partner: UNT Libraries Government Documents Department
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Final Hazards Summary Report to the Advisory Committee on Reactor Safeguards on a Research Reactor for the Massachusetts Institute of Technology

Description: From summary: Report on the location, final design, and hazards analysis of the Massachusetts Institute of Technology Reactor Facility. It is hoped that the reactor plans described in this report may be approved from the safety standpoint, so that a license and construction permit for the facility may be granted and construction started.
Date: 1956
Creator: Thompson, Theos Jardin; Benedict, Manson; Cantwell, Thomas & Axford, Roy A.
Partner: UNT Libraries Government Documents Department
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The Pile Safety Circuit

Description: The present report is concerned with the electronic relay which, upon the reaching of a pre-determined value of ionization current in the associated chamber, actuates the safety rod release mechanism. The are here proposed two independent suggestions: (1) An improved trip circuit of such sensitivity and stability as to allow it to be actuated by a signal directly from the chamber without the necessity of interposing intermediate amplifier stages. The value of chamber current at which tripping occurs is stable to +- 0.4%. (2) A triple-wound relay to prevent shut-downs of the pile which would otherwise be caused by development of defects in the safety circuits.
Date: April 14, 1944
Creator: Nierman, Leonard G.
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Project: Status Report on Reactor Safeguards Analysis

Description: The purpose of this report is to describe the nuclear power plant for the N.S. Savannah and the program in progress for the analysis of potential hazards associated with the operation of a nuclear merchant vessel. Particular emphasis is given to the safety features embodied both in the design and operation of the plant.
Date: May 9, 1958
Creator: The Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Fuel Failure Detection in the Heavy Water Components Test Reactor

Description: The Heavy Water Components Test Reactor (HWCTR) is a pressurized reactor, cooled and moderated with D2O, and has the capability of testing fuel assemblies under operating conditions of coolant flow, temperate, and pressure that are typical of those proposed for modern power reactors. The report contains (1) description of the four systems used for failed element detection, (2) discussion of the laboratory analyses of water samples used a as backup for the fuel failure instruments, (3) description of 3 monitors, Cyclic Air Sampling Monitor, Stack Gas Activity Monitor, Health Physics Building Monitors, (4) normal full power activity readings, (5) discussion of the experience during fuel failure.
Date: September 20, 1963
Creator: Kiger, E. O.
Partner: UNT Libraries Government Documents Department
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Physics of Reactor Safety, Quarterly Report: April-June 1976

Description: Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division including: reactor safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPP) Planning and Experiments Group.
Date: 1976?
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department
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Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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SRE Instrumentation and Control

Description: Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date: May 21, 1956
Creator: Hall, R. J.
Partner: UNT Libraries Government Documents Department
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Reactor Safety, Quarterly Progress Report, February-April 1954

Description: "The composition of the solder for the solder plug has been set as the tin-silver eutectic. Final tests on this solder show that life expectancies much longer than 6 months are probable with the current design. The design of the heater tube to contain the solder plug has been settled. This consists of a copper tube impregnated with U235O2. Arrangements have been made to have test specimens fabricated by powder metallurgy techniques. The equipment for the MTR in-pile test of trigger element response times has been largely completed and tested. The design of the complete inner capsule for the BF3 safety element has been developed as well as the cladding technique. Mock-up elements have been tested in the Hanford test reactor to determine the control that may be obtained with elements of this type, although the analysis of the results has not been made. Prototype elements are also ready for testing in the test pile, except for loading with B10F3. Experiments have been designed and submitted for approval for production pile tests of prototype."
Date: October 1, 1954
Creator: Huston, Norman E.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the Battelle Research Reactor

Description: From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date: April 4, 1955
Creator: Chastain, J. W.; Redmond, R. F.; Klickman, A.; Anno, J. & Fawcett, S. L.
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Description: Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
Partner: UNT Libraries Government Documents Department
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Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination

Description: Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generator. Decontamination factors of greater than 50 were obtained in loop tests using the above treatment. Corrosion and metallurgical results indicated a total penetration of less than 0.01 mil on annealed Type 304 stainless steel with no evidence of any deleterious effects.
Date: February 15, 1959
Creator: Zegger, John L. & Pancer, Guyon P.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Reactor Safety and Physical Properties Studies Annual Report, July 1975-June 1976

Description: A report of the work on Reactor Safety and Physical Property Studies performed in the Chemical Engineering Division at Argonne National Laboratory is given for the period July 1975-June 1976.
Date: 1976?
Creator: Leibowitz, L.; Blomquist, R. A.; Fink, J. K.; Finn, P. A.; Fischer, D. F.; Green, D. W. et al.
Partner: UNT Libraries Government Documents Department
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Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Partner: UNT Libraries Government Documents Department
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Level and Leak Indicators

Description: The following report provides results taken from a sodium level indicator developed at Sacandaga using electrical resistance as the principle.
Date: December 20, 1949
Creator: Vandenberg, L. B.
Partner: UNT Libraries Government Documents Department
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Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Partner: UNT Libraries Government Documents Department
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