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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise ins… more
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Measuring Principle : Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.
Date: March 28, 1960
Creator: Burgwald, G. M. & Stone, C. A.
Partner: UNT Libraries Government Documents Department
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An Experimental Gamma Irradiator for Hospital Sterilization

Description: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date: March 7, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
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Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
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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Scope report Safety Circuit Trip Identification System

Description: The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.
Date: March 23, 1960
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
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Some considerations concerning the accuracy of power level calculations in the context of the control of SS materials

Description: This report investigates a study of the accuracy of the power level calculations. Some characteristics of this calculation can be adduced but the accuracy in the sense of freedom from bias leads to an impasse. It presumes that there is another measurement for comparison purposes for which there are engineering reasons to believe, the inherent error is smaller. For the power level values as calculated by the Foxboro Power Level Calculator no such measurement or calculation exits. However, the ca… more
Date: March 14, 1960
Creator: Stewart, K. B.
Partner: UNT Libraries Government Documents Department
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Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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The poison spline system

Description: No Description Available.
Date: March 10, 1960
Creator: Smithers, R. M.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for standard BDF geometry at low tube powers

Description: Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor op… more
Date: March 24, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
open access

Status report - C Reactor process tubes

Description: Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.
Date: March 21, 1960
Creator: Miller, N. R.
Partner: UNT Libraries Government Documents Department
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Flux distribution problems at C Reactor

Description: This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.
Date: March 16, 1960
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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Resume of KER Loop irradiation tests for 1957, 1958, and 1959

Description: In 1957 three of the four high temperature recirculating loops in KE Reactor were put into service and in 1958 the fourth loop was started up. The primary purpose of the loops has been high temperature irradiation testing of fuel elements in support of the NPR fuel element development program, although tests have been run to provide information for PRTR fuel development and high temperature aluminum corrosion programs. Coolant technology studies relating to activity build-up, crude formation, c… more
Date: March 28, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Piping Changes for Increased Production at B, D, DR, F, C and H Reactors calculations

Description: On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing … more
Date: March 24, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Automatic alum feed device to produce water of any given clarity

Description: This report documents the research and testing of an automatic alum feed process at the Hanford reservation. This process generates water of varying qualities which is used to cool fuel elements in nuclear reactors.
Date: March 7, 1960
Creator: Conley, W. R. & Pitman, R. W.
Partner: UNT Libraries Government Documents Department
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Burst testing of irradiated Zircaloy tubing. Revision 1

Description: An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diam… more
Date: March 4, 1960
Creator: Kahle, V. E.
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
open access

An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
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