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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

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

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

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

Physics of Reactor Safety Quarterly Report: July-September 1975

Description: Quarterly progress report discussing work done in Argonne National Laboratory's Applied Physics Division for the Division of Reactor Safety Research. It includes reports on 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 Phys!cs Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group.
Date: 197u
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department

The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Description: Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date: October 1964
Creator: Silker, W. B. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department

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

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

Physics of Reactor Safety, Quarterly Report: October-December 1975

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 (ZPR) Planning and Experiments Group.
Date: 197u
Creator: Argonne National Laboratory. Applied Physics Division.
Partner: UNT Libraries Government Documents Department