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100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report

Description: A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is rad… more
Date: May 1, 1960
Creator: Weddell, J. B. & Bloom, J.
Partner: UNT Libraries Government Documents Department
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1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES

Description: The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for … more
Date: May 1, 1963
Creator: Kelber, C.N.
Partner: UNT Libraries Government Documents Department
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1965 audit of SRP radioactive waste

Description: This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1965. Total quantities of radioactive waste released from plant startup through 1965 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the R… more
Date: May 1, 1966
Creator: Ashley, C.
Partner: UNT Libraries Government Documents Department
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2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE

Description: Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The co… more
Date: May 1, 1962
Creator: Chaumont, J. M. & Koerner, J. A.
Partner: UNT Libraries Government Documents Department
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ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY

Description: The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quart… more
Date: May 25, 1960
Creator: Canfield, R. T.; Rausch, W. P.; Vallario, E. J.; Young, R. G. & Henderson, S. K.
Partner: UNT Libraries Government Documents Department
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ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT

Description: The concentrations of and activities due to N/sup 16/ and N/sup 17/ in the HFIR primary coolant water were calculated. At the pressure vessel exit, the N/sup 16/ activity is 3.9 x 10/sup 6/ dis/secml and the N/sup 17/ activity is 6.9 x 10/sup 2/ dis/sec-ml. Comparison of the N/sup 16/ activity with the data obtained from the ORR water system indicates that the calculated results are slightly conservative. (auth)
Date: May 25, 1960
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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Adjustment of total control parameters for C Reactor

Description: The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New … more
Date: May 22, 1962
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963

Description: Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion co… more
Date: May 1, 1963
Creator: Goeddel, W.V.; Sandefur, N.L. & White, J.L.
Partner: UNT Libraries Government Documents Department
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Alpha Particle Ionization of Argon Mixtures--Further Study of the Role of Excited States

Description: BS>The average energy required to form an ion pair, W, when alpha particles are absorbed in mixtures of argon with other gases is studied. The other gases were selected on the basis of their ionization potentials. One group consists of representative gases that have ionization potentials below that of Ar (15.77 ev) and above the doublet metastable state of Ar (11.49 and 11.66 ev). This list includes methane, carbon dioxide, nitrous oxide, xenon, and krypton. The other group of special interest … more
Date: May 23, 1963
Creator: Borner, T. E.; Hurst, G. S.; Edmundson, M. & Parks, J. E.
Partner: UNT Libraries Government Documents Department
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Analog Computer Study of the MSR-ORR in-Pile Pressurized Water Loop No. 1

Description: A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using the Reactor Controls Analog Facility. Computer curves show the predicted response of the loop temperatures to normal load changes and component failure accidents. Except for complete flow stoppage, which was not investigated here, the safety system was shown to be adequate in curbing loop temperature excursions due to postulated accidents. (auth)
Date: May 1, 1960
Creator: Ball, S. J.
Partner: UNT Libraries Government Documents Department
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Analysis of alternatives: Plutonium button-line improvements

Description: Reduction of Pu nitrate solution to metal is accomplished in the button line portion of the Remote Mechanical Line. Several areas of deficiency exist in the facility, which must be corrected in order to maintain continuity. In December 1963, a study was undertaken to define and evaluate the operational and economic parameters pertinent to deciding to improve or replace the button line. This paper documents the study and presents the conclusions and recommendations.
Date: May 1, 1964
Creator: Johnson, B. M.; Smith, V. W.; Swain, E. O.; Szulinski, M. J. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
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Analysis of LASL Core Bundling Pressure Test

Description: This is an analysis, based on a test conducted by LASL personnel, to determine whether relative expansion of two pieces of graphite under bundling loads would result in failure of the graphite.
Date: May 1, 1963
Creator: Brussalis, William
Partner: UNT Libraries Government Documents Department
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