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Status Report on the Argonne Advanced Research Reactor

Description: The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and constructio… more
Date: November 1, 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Evaluation of Wire Scanner for SM-1

Description: Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location,… more
Date: November 22, 1961
Creator: Kemp, S. N.
Partner: UNT Libraries Government Documents Department
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FAST BREEDER REACTOR THERMOCOUPLE DEVELOPMENT.

Description: Studies of very high-temperature thermocouple characteristics for instrumentation and electrical components used in fast breeder reactors showed that the thermoelectric emf produced along BeO, HfO{sub 2}, or ThO{sub 2} insulators can affect the output of the thermoelements. Bare-wire thermocouples are influenced by environment. Radiation effects on W versus W - Re thermocouples in the ORR after ~ 2 months in a 1.2 x 10{sup 14}n/cm{sup 2}-sec thermal and 2.1 x 10{sup 13}n/cm{sup 2}-sec fast flux… more
Date: October 31, 1969
Creator: Funston, E.S. & Kuhlman, W.C.
Partner: UNT Libraries Government Documents Department
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Calculation and Measurement of the Transient Temperature in a Low- Enrichment UO$sub 2$ Fuel Rod During Large Power Excursions

Description: The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from appr… more
Date: May 18, 1962
Creator: Houghtaling, J. E.; Quigley, T. M. & Spano, A. H.
Partner: UNT Libraries Government Documents Department
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EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT

Description: The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, prim… more
Date: March 27, 1962
Creator: Neill, F.H. & Michelson, C.
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediat… more
Date: March 10, 1961
Creator: Hankins, D. E.
Partner: UNT Libraries Government Documents Department
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FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962

Description: The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiatio… more
Date: June 1, 1962
Partner: UNT Libraries Government Documents Department
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Reactor Controls Reliability and Maintenance at the ORR

Description: Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a de… more
Date: August 28, 1962
Creator: West, K.W.
Partner: UNT Libraries Government Documents Department
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The Specific Heat of Dysprosium Metal Between 0.4 and 4 K

Description: Submitted to Illinois Inst. of Tech., Chicago. A He/sup 3/ cryostat was built to measure the specific heat of rare earth metals which have a component, at low temperatures, attributable to the electrons in the incomplete 4f shell. The specific heat of dysprosium from 0.4 to 4.2 deg K was measured. Pertinent theories about specific heats are outlined. The apparatus included the cryostat, vacuum and He/sup 3/ systems, calorimeter, carbon thermometer, heater, and magnetic thermometer. The experime… more
Date: August 1, 1962
Creator: Guenther, R. A.
Partner: UNT Libraries Government Documents Department
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EBWR Reactor Pressure Vessel Revisions for Instrumentation and Increased Steam Output

Description: The procedures developed and utilized for the addition of connections to the EBWR pressure vessel after three yesrs of intermittent operation at the 20- Mw(t) design heat output are described. Major nozzle connections to the pressure vessel were made during two separated periods and under different conditions of vessel content. The details of the conversion sre discussed under the following topics: nozzle design, preparations, and nozzle installation. Diagrams and photographs are included. Radi… more
Date: January 1, 1962
Creator: Kettles, T.L. & Balai, N.
Partner: UNT Libraries Government Documents Department
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Periodic Intercalibration of Temperature Sensing Elements, Core I, Seed I. Test Results T-641306

Description: BS>Intercalibration data for various temperature sensing elements in the reactor coolant system are obtained and compared with calculated source activity levels and observed channel levels. The readings of 20 of the 62 core thermocouples were either less than 400 deg F, which was off scale on the recorder, or were plus or minus 20 deg F from the calibrating resistance thermometer temperatures. The remainder of the readings were within plus or minus 3% of the temperatures of the calibrating ther… more
Date: October 24, 1960
Partner: UNT Libraries Government Documents Department
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