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Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator

Description: Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, … more
Date: October 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modified Purification System Performance Test. Core I, Seed 2. Test Results (T-641124). Section 1

Description: An investigation was conducted to establish an operating procedure for flushing water through a purification system demineralizer which was out of service for an extended period, and to determine the demineralizer serviceability. (J.R.D.)
Date: September 14, 1960
Creator: Duquesne Light Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experience with anthracite - sand filters

Description: The General Electric Company operates eight large filter plants for the Atomic Energy Commission at the Hanford works in the state of Washington. Because of the importance of water to the process, research and development on water treatment has been an important part of the overall Hanford research and development program. The research and development on water treatment has resulted in important capital and operating savings and in the production of better quality water. It is the purpose of th… more
Date: November 11, 1960
Creator: Conley, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy release per fission in the Hanford reactors

Description: The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.
Date: February 12, 1960
Creator: Morgan, W. C. & Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Variable goal exposure plans for production type fuel elements

Description: The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throug… more
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of quality certification data: WARP, TFC and delta OD{sub 2} as a function of reactor operating conditions

Description: This report is the second in a series on the definition of performance of irradiated fuel elements as measured by the Quality Certification Program. Objectives of this analysis are to establish empirical mathematical relations which fit observed data from > 2000 fuel elements measurements for WARP, TFC, and DELTA OD{sub 2}, as a function of reactor conditions (power, surface temperature, time).
Date: November 23, 1960
Creator: Hagie, L. T. & Jaech, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Significance of operating experience with poison splines at KE Reactor

Description: The demonstrated operating efficiency performance which has resulted from poison spline usage forces an economic decision concerning the self-supported and bumper fuel element programs. As originally conceived the projection fuel elements would preclude the insertion of a spline under the fuel charge; thus it is very important that means be devised either to make poison spline usage compatible with future pile loadings or to demonstrate that some other supplementary control system, which is com… more
Date: July 15, 1960
Creator: Franklin, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Judgment analysis of comparative C-64-F and X-8001-F alloy canned fuel element performance

Description: Fuel element component procurement requires a considerable lead time (three to four months after design is completed). Collection of data and statistical analyses to evaluate the performance of these components takes even longer. There is often reluctance to disturb the status quo in these matters without engineering recommendations; these are usually not given until the parameters are defined quantitatively with a high statistical level of significance. The purpose of this analysis is to take … more
Date: April 19, 1960
Creator: Brown, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTIVITY LIFETIME 5091.4-5806.1 EFPH. CORE I, SEED 1. Test Results T- 612118-B

Description: The Shippingport Atomic Power Station was operated for 715 EFPH from Ang. 11 to Oct. 7, 1959, in order to determine the performance characteristics reliability, stability, and lifetime variation of the core during rated power operation for an extended period of time. The plant was operated at successively lower power levels of 60, 43, and 17 Mwe to extend the Core I, Seed 1 lifetime. Logs and tables are included which present the events and all recorded data in this period. (D.L.C.)
Date: August 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP I POWER CONVERSION SYSTEM ALTERNATOR DEVELOPMENT. Period covered: February 1, 1957 to June 30, 1959

Description: Alternator development for the SNAP 1 power conversion system is described. A radial air-gap permanent-magnet 6-pole single-phase 2600-cps alternator, rated at 536 watts, 0.8 power factor, and 115 volts was selected. Discussion of requirements and specifications, design and performance, test facilities, and conclusions are included. (J.R.D.)
Date: June 20, 1960
Creator: Morgan, H.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance Characteristics of an Electromagnetic Pump

Description: >The performance characteristics of small linear-induction electromagnetic pumps suitable for high-temperature liquid-metal test-loop operation were examined. Also, methods by which the performance of such pumps may be improved were investigated. The phenomenon of fluid wetting of the pump duct wall and the use of side bars provide powerful tools for improving the linear-induction-pump performance characteristics. Full advantage of the improved performance can be obtained if the hydraulic losse… more
Date: August 1, 1960
Creator: Thompson, D. H. & Fisher, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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QUARTERLY REPORT OF THE LABORATORY DIRECTOR FOR THE PERIOD JULY 1, 1959 TO SEPTEMBER 30, 1959

Description: The third quarter of 1959 was occupied with putting the finishing touches on components of the Two-Way Model, adjusting the magnetic field to the required magnitude at all points, and life testing completed components. The present status of the model components is given including the magnet, vacuum tank, equipment for acceleration, and injector. Status of various study groups is discussed. A list of papers published, submitted for publication, and presented at meetings for the period Oct. 1958 … more
Date: October 31, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Aerosol research at Hanford and engineering applications to production reactors

Description: When the construction of the confinement facilities for Hanford production reactors is completed, the potential for contaminating the environment with accidentally released fission products will be greatly reduced. This was demonstrated already when rupture debris burned in the rear face area of one of the reactors in which the fog spray was installed and ready for service. The fog spray effectively prevented the spread of contamination to the ventilation equipment downstream of the rear face e… more
Date: October 24, 1960
Creator: Linderoth, C. E.; Heacock, H. W. & Schwendiman, L. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear … more
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Civilian Power Reactor Program. Part 3. Status Report on Gas-Cooled Reactors as of 1959. Book 8

Description: The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel prototype and for a large natural- uraniumfueled plant. Current technical status is discussed in terms of reactor physics, heat transfer and fluid flow, core mat… more
Date: January 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Valve Stem Freeze Seal for High-Temperature Sodium

Description: Valve stem freeze seals for high-temperature service in advanced sodium- cooled reactor systems were studied. An experimental model, suitable for use with a 6-in. size valve, operated satisfactorily under a variety of conditions. The freeze seal region was cooled by natural convection to ambient atmosphere; cooling by both circumferential and longitudinal finned sections was experimentally studied. The operating conditions included sodium bulk temperatures up to 1300 tained F, sodium pressures … more
Date: July 30, 1960
Creator: McDonald, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SNAP I POWER CONVERSION SYSTEM MATERIALS DEVELOPMENT. Period covered: February 1, 1957 to June 30, 1959

Description: Investigations of materials for use in connection with the SNAP I mercury Rankine cycle power conversion system are discussed. Test programs are outlined and results are tabulated for each candidate material. Several nonmetallic materials and processing procedures were developed which enabled uncooled high-performance electric machinery to operate at 550 deg F in mercury vapor. (J.R.D.)
Date: June 20, 1960
Creator: Hambor, V. F. & Owens, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SNAP Programs, Tasks 2, 3, 5 and 6 Quarterly Progress Report No. 2, January to March 31, 1960

Description: System Design. A chem-milled outer skin, an improved thermoelectric element adjustment and access plug, a flexible stainless steel-aluminum joint welded via ultrasoric techniques, a flexible hot shoe assembly, and thermal hydrauilc heat dump system were incorporated into the design of the environmental and ground test generators. Materials Analysis. Burnup studies on fuel forms were continued with CeF/sub 3/ and CeO/sub 2/. SiC/sub 2/ appeared to be the most promising addition to CeO/sub 2/. Te… more
Date: December 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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