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PL FINAL DESIGN REPORT. VOLUME II. PLANT DRAWINGS

Description: Plant drawings for the final design for the Army Reactor (PL-2) are presented. Two hundred and twenty-eight figures are included. (M.C.G.)
Date: June 30, 1961
Creator: Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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The Boron-Carbon System: Final Technical Report, May 1, 1960 - April 30, 1961

Description: Abstract: The boron-carbon equilibrium diagram has been determined by X-ray, metallographic, and thermal analysis of sintered and arc-cast alloys. A single carbide having a range of solubility from approximately 9 to 20 a/o carbon and melting congruently exists in the system. The terminal solubility of carbon in boron is 0.1-0.2a/o. The freezing reaction at the composition and melting temperature of elemental boron; there is a eutectic reaction at 29a/o carbon and 2375 degrees Celcius. No allot… more
Date: June 7, 1961
Creator: Elliott, Rodney P.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System : Quarterly Report No. 4 Covering the Period from March 1, 1961 to May 31, 1961

Description: This is the fourth quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: June 23, 1961
Creator: Haffner, J. W.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT - MARCH THROUGH MAY1961

Description: The study of meteorite Murray has been reported in previous Quarterly Reports. This report gives further results with Murray, and information on another meteorite, Orgueil. A sample of Orgueil was sent from the Museum National d Histoire Naturelle, Paris. It fell in several pieces over an area of 2 square miles near Orgueil, France, in 1864. The elemental analysis of this meteorite is shown in Table 1. They extracted a 10.07-g sample of this meteorite with water, using the same procedure as tha… more
Date: June 29, 1961
Partner: UNT Libraries Government Documents Department
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Reduction of the amount of dichromate added to reactor cooling water: Interim report, Production Test-IP-321-A

Description: Reduced process water treatment costs and incidental benefits of smaller hexavalent chromium discharge to the Columbia River provided incentives to conduct a half-reactor production test. The sodium dichromate (Na{sub 2} Cr{sub 2} O{sub 7}2H{sub 2}O) concentration in process water supplied to the far side of 105-C was lowered from a nominal value of 1.8 to 1.0 parts per million (ppM). This test was started September 26, 1960 and is still in progress. However, a sufficient amount of data is avai… more
Date: June 19, 1961
Creator: Nesselson, E. J.
Partner: UNT Libraries Government Documents Department
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KER-3 operating report test K-3-13, PT-1P-363-A. Irradiation of ZR-2 jacketed enriched single tube fuel elements in the KER Loops

Description: The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.
Date: June 12, 1961
Partner: UNT Libraries Government Documents Department
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Radiation Safety and Control Training Manual

Description: Introduction: The Laboratory follows the recommendations of the National Committee on Radiation Protection concerning permissible exposure limits for those working with radiation. A system of controls and regulations has been established which should ensure that no person at the Laboratory will receive more than the permissible exposure. This manual is intended to provide the minimum background necessary for intelligent cooperation with the regulations.
Date: June 1, 1961
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department monthly report, May 1961

Description: Output of fuel elements during May was 107% of forecast. Engineering of present reactor fuels and N-Reactor fuel development are discussed. (DLC)
Date: June 7, 1961
Partner: UNT Libraries Government Documents Department
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Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Description: Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.
Date: June 30, 1961
Creator: Chittenden, W. A. & Hoveke, G. F.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: May 1961

Description: The monthly report for the Hanford Laboratories Operation, May 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.
Date: June 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Boiling tests on DR-Downcomer

Description: No Description Available.
Date: June 16, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
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Reactor Flow Studies : Full Scale Model Flow Tests

Description: From foreword: This report contains the test results and analysis of test results of flow studies and reactor vessel internals. Tests were performed at, below, and above the PM-1 design flow rate to observe flow distribution and pressure drops within the reactor vessel, as well as the overall reactor vessel pressure drop.
Date: June 1961
Creator: Taylor, W. J.; Starr, I. & Baer, R. L.
Partner: UNT Libraries Government Documents Department
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SNAP Programs Quarterly Progress Report, Task 8--Stontium-90 Fuled Thermoelectric Generator Development: Number 1, November 1, 1960-January 31, 1961

Description: From summary: The SNAP 7 program is being conducted for the purpose of developing four radioisotope-fueled thermo-electric power generation systems. An important phase of this program is the processing of Strontium-90 into heat sources for these systems. The current effort involves the design and engineering analysis of two of the four thermo-electric generators.
Date: June 1961
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of a Zircaloy-2 clad, natural uranium thermocouple fuel element in KER-1

Description: During the 0000--0800 shift on August 21, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 2, 3 and 4 monitors indicating a possible fuel element failure in Loop 1. The KER Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 1.
Date: June 5, 1961
Creator: Demmitt, T. F.
Partner: UNT Libraries Government Documents Department
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Supplement A: PT IP-105-C graphite power coefficient determination

Description: The objective of this supplement is to review the basis, justification and procedure so that this production test may be used permitting a determination of minimum downtime, when advisable for improving moderator coefficient data as function of exposure.
Date: June 16, 1961
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Explanation of the high temperature obtained in the Intermediate Power Test

Description: It is now generally known by those working on Tory II-A that the average maximum fuel element wall temperature obtained during the Intermediate Power Test was somewhat higher than the 2250 degrees F design value. The purpose of this report is to explain how this occurred.
Date: June 16, 1961
Creator: Barnett, C.
Partner: UNT Libraries Government Documents Department
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Notes on reactor operation within a product specification

Description: A product specification will impose operating problems for the HAPO reactors and the separation facilities. A preliminary analysis of several methods of operating have been considered using a linear program analysis. This document considers some of the implications. A linear programmed study of HAPO reactors was made in which six percent Pu was maximized under several reactor plans.
Date: June 9, 1961
Creator: Lang, L. W. & Neef, W. I.
Partner: UNT Libraries Government Documents Department
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