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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)

Description: The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, specia… more
Date: November 30, 1962
Creator: Gwin, R. & Murray, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR

Description: Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron mult… more
Date: November 15, 1961
Creator: Cheverton, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Single Element Flow Tests for Type 3 (SM-2) Fuel Elements in SM-1, SM-1A, and PM-2A Cores

Description: Channel-to-channel flow distribution within Type 3 (SM-2, stationary and control rod fuel elements modified for use in the SM-1, SM1-1A, and PM-2A core support structures and control rod tubes was measured in single element flow testing. Plots of channel-to-channel flow distribution and element pressure drop at various element flow rates are given. Flow distribution for the top-orificed SM-1A and PM-2A stationary elements was within the plus or minus 12% deviation from element average utilized … more
Date: November 27, 1961
Creator: Krause, P. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supporting Analysis and Derivation of Dimensional Tolerance Specifications for Core II of SM-1A & PM-2A

Description: A method is presented for translating inspection measurements of fuel plate spacing to obtain minimum coolant channel clearances under reactor operating conditions. Considerations of fuel plate ripple growth and the inspection procedure used are included. The method is applied to establish dimensional tolerance specifications used for the procurement of SM-1A and PM-2A Core II. (auth)
Date: November 1, 1961
Creator: Brondel, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961

Description: Fifty-seven papers and l7 abstracts of papers are presented in the report. Fifty two of the papers are abstracted separately; in addition, a single abstract is written to cover the section on Plasma Physics Theory, which contains 3 papers and 8 abstracts of papers. The two brief papers not abstracted separately are concerned with fast neutron detection, and homogeneous critical assemblies of 3%enriched UF/sub 4/-paraffin systems. (T.F.H.)
Date: November 17, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Evaluation of the Combustion Hazard to the Experimental Gas- Cooled Reactor-Preliminary Burning Rig Experiments

Description: >An assembly was constructed which simulated the moderator coolant annulus in the Experimental Gas-Cooled Reactor. This assembly was preheated to various temperatures and air was passed through the coolant annulus. Under certain conditions it was demonstrated that self-sustained combustion of the graphite could occur. Rates of temperature rise were generally less than 1 deg C/ min until the graphite temperature exceeded 700 deg C and then rise rates became very high. In these cxperimcnts, the a… more
Date: November 1, 1961
Creator: Dahl, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST REACTOR SHAPE FACTORS AND SHAPE-DEPENDENT VARIABLES

Description: Existing experimental data on the variation of reactivity with core geometry are reviewed. Four typical fast neutron systems are analyzed to predict: (l) the variation of critical mass with cylindrical core geometry (core and reflector composition are held fixed); (2) the reactivity worth of fuel at the radial core boundary as a function of cylindrical core geometry; and (3) the geometric variation of heat removal parameters; these include the ratio of: (a) Maximum power density to average powe… more
Date: November 1, 1961
Creator: Loewenstein, W.B. & Main, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NON-DESTRUCTIVE ANALYSIS OF URANIUM IN GRAPHITE FUEL ELEMENTS BY NEUTRON ACTIVATION

Description: A method is presented for the determination of uranium (as U/sup 238/) in uraniuni-loaded graphite fuel elenients by a non-destructive, direct radioactivity analysis technique. A 200-cbannel pulse-height analyzer, equipped with a 3 in. x 3 in. NaI(Tl) crystal, is used to measure the Np/sup 239/ radioactivity of the neutron-irradiated samples. The amount of U/sup 238/ in the test samples is deterimined quantitatively by comparing the Np/sup 239/ radioactivity induced in each sample with the Np/s… more
Date: November 28, 1961
Creator: Bate, L.C.; Hampton, W.J. & Leddicotte, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PULSE COLUMN DESIGN

Description: A stagewise approach was used in a theoretical analysis of pulse columns. In the analysis the column was arbitrarily divided into discrete stages comprising that part of the column between two adjacent perforated plates. The operation of the pulse column was described mathematically using material balance equations, and a design method was derived which used two stage lines and two operating lines, one set for the pulse generator upstroke and one set for the downstroke. Assuming equilibrium con… more
Date: November 1, 1958
Creator: Burkhart, L.E. & Fahien, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LONGITUDINAL DISPERSION IN SOLVENT-EXTRACTION COLUMNS: PECLET NUMBERS FOR ORDERED AND RANDOM PACKINGS

Description: Dispersion phenomena in packed beds in both axial and radial directions were studied to provide basic data for extraction-tower design. Nine different beds were used, involving regular and random arrangements of spheres, and random arrangements of Raschig rings and Intalox saddles. For one-phase flow a wide range of Reynolds numbers was used (5 to 2000), covering regions of laminar, transition, and turbulent flow. For the axial Peclet number, different constant values were found in the turbulen… more
Date: November 1, 1957
Creator: Jacques, G.L. & Vermuelen, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TURBULENT HEAT TRANSFER FROM A MOLTEN FLUORIDE SALT MIXTURE TO SODIUM- POTASSIUM ALLOY IN A DOUBLE-TUBE HEAT EXCHANGER

Description: Mixtures of fluoride salts were found to show promise for the circulating-fuel application. An experiment to measure the heat transfer characteristics of the fluoride salt mixture NaF-- ZrF/sub 4/-- UF/sub 4/ was performed. A correlation of film heat transfer coefficients and the effect on heat transfer of deposits resulting from corrosion or mass transfer of container materials are reported. (J.E.D.)
Date: November 1, 1954
Creator: Salmon, D.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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