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13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8

Description: Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date: August 1, 1960
Creator: Bloom, J. L.
Item Type: Refine your search to only Report
open access

40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959

Description: The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading… more
Date: September 1, 1960
Item Type: Refine your search to only Report
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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies

Description: ESE-171: This EN run was made to determine if there is any relationship between the H-5 transistor electrical characteristics, the assembly processes, and slow warm-up of the MC-890 Power Supply. Included is the test data on the H-5 transistors and the results of the High Temperature Life Test (185 {degrees}F) of 380 MC-890 Power Supplies.
Date: September 1, 1960
Creator: Ling, R.F.
Item Type: Refine your search to only Report
open access

ABRAC--AN IBM-704 THREE DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS

Description: ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date: March 1, 1960
Creator: Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Item Type: Refine your search to only Report
open access

Accurate Micrometer for Corrosion Samples

Description: A micrometer that utilizes eddy current techniques is described. The gage is capable of measuring nominal 0.5000-in. aluminum rods to an accuracy of plus or minus 0.00005 in., and is unaffected by residual nonconductive surface filins such as oxides or corrosion products. (auth)
Date: June 1, 1960
Creator: Woodward, W. J.
Item Type: Refine your search to only Report
open access

THE ADIABATIC ELASTIC MODULI OF SINGLE-CRYSTAL ALPHA URANIUM AT 25 C. Work completed: January 1958. Partial Report-Metallurgy Program 4.1.16

Description: The 9 single-crystal elastic moduli pertaining to principal crystallographic axes of alpha U at 25 deg C were determined from measurements of high-frequency wave velocities for 21 modes in seven single-crystal specimens, using the phase-comparison method of McSkimin. From the results the elastic compliances, compressibilities, and Poisson"s ratios were computed for the principal axes. Th variations with crystal direction of the stiffness moduli, Young's moduli, and rigidity moduli were plotted.… more
Date: June 1, 1960
Creator: Fisher, E. S.
Item Type: Refine your search to only Report
open access

THE ADVANCED TEST REACTOR-ATR FINAL CONCEPTUAL DESIGN

Description: The results of a study are presented which provided additional experimental-loop irradiation space for the AECDRD testing program. It was a premise that the experiments allocated to this reactor were those which could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for a reactor producing perturbed neutron fluxes exceeding 1O/sup 15/ thermal n/cm/sup 2/-sec and 1.5 x 1O/sup 15/ epithermal n/cm/sup 2/-sec. To accommodate th… more
Date: November 1, 1960
Creator: deBoisblanc, D.R. et al
Item Type: Refine your search to only Report
open access

Advanced Thermoelectric Power System. Final Report

Description: Development of a radioisotope-fueled thermoelectric power-conversion system for the SNAP program is discussed. The generator operates at somewhat less than 1% over-all efficiency, has a power output of approximately 1.45 watts, and has a specific power of 0.l42 watts per pound. The power-flattening device did not perform as expected. A second generator is also described which produces a maximum power of 1.6 watts, has a maximum efficiency of 1.20%, and has a specific power of 0.32 watts per pou… more
Date: January 1, 1960
Creator: Harvey, R. J.
Item Type: Refine your search to only Report
open access

LOS ALAMOS POWER REACTOR EXPERIMENT NO. II, LAPRE II

Description: Design features and operating characteristies of the Los Alamos Power Reactor Experiment No. II are discusssd. Results of performance tests and of an examination conducted after disassembly of the reactor are presented. Recommendations for work on uranium phosphate fueled reactors are made. (auth)
Date: April 1, 1960
Creator: Clark, R.A. comp.
Item Type: Refine your search to only Report
open access

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.
Item Type: Refine your search to only Report
open access

Analysis of the Moon's Surface by Nuclear Reactions

Description: Introduction. With the imminence of non-destructive landings of small instrumented payloads on the moon, many suggestions are being put forth as to methods of analyzing its surface. It is the purpose of this report to present a body of information which, it is hoped, will be useful in examining the feasibility of an early nuclear experiment to determine the elemental constituents of the lunar surface. The reasons for considering a nuclear approach is that it may be possible to perform an analys… more
Date: April 1, 1960
Creator: Martina, E. F. & Schrader, Carlton D.
Item Type: Refine your search to only Report
open access

Anion Exchange Recovery of Plutonium From Reduction Residues

Description: An anion exchange process was demonstrated for the recovery of Pu from waste produced in the reduction of Pu salts to the metal. Pu in a highiy salted 6M nitric acid solution, derived from the dissolution of slag and crucible waste, was separated from impurities by absorbing the Pu(IV) nitrate complex on the anion exchange resin and subsequentiy eluting with dilute nitric acid. A flowsheet for plant operation is presented. (auth)
Date: February 1, 1960
Creator: Russell, E. R.
Item Type: Refine your search to only Report
open access

ANION EXCHANGE SEPARATION OF TRIVALENT ACTINIDES AND LANTHANIDES

Description: A process for separating americium and curium from rare earths by anion exchange based on selective chloride complexing was developed and tested on a laboratory scale. The separation is accomplished by sorption of americium, curium, and rare earths on Dowex 1-10X resin from a solution of 8 M LiNO/dub 3/ followed by selective elution of rare earths with 10 M LiCl and americium-curium elution with 1 M LiCl. In a laboratory demonstration of this process, greater than 99.5% of americium tracer cont… more
Date: June 1, 1960
Creator: Lloyd, M. H. & Leuze, R. E.
Item Type: Refine your search to only Report
open access

ANNUAL SUMMARY RESEARCH REPORT IN CHEMISTRY, JULY 1, 1959-JUNE 30, 1960

Description: Pilot-plant work on ion exchange separation of rare earths indicates that elution with HEDTA on hydrogen-form resin should conserve Sc. Then, after Sc, Lu, Yb, Tm, and Er are diverted to an auxiliary bed, the remaining rare earths can be resolved with EDTA. Data from investigations of rare-earth glycolate solubilities at 20 and 60 deg C are tabulated. In other work, the effectiveness of glycolic acid for fractionally precipitating rare earths was investigated, and the solubilities and compositi… more
Date: September 1, 1960
Item Type: Refine your search to only Report
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ANNUAL SUMMARY RESEARCH REPORT IN ENGINEERING FOR JULY 1, 1959-JUNE 30, 1960

Description: Work was continued on the determination of size and distribution of dispersed phase droplets in a pulse column. The droplet behavior and dispersed phase hold-up in Yorkmesh packing was studied with an equilibrated system of methyl isobutyl ketone and water with the ketone phase dispersed. An investigation is being made of the recovery of copper and EDTA from rare-earth ion exchange wastes. The effect of vapor properties on entrainment from bubble cap trays is being investigated. The design, con… more
Date: August 1, 1960
Item Type: Refine your search to only Report
open access

Annual Summary Research Report in Physics, July 1, 1959-June 30, 1960

Description: Research in theoretical and experimental physics is summarized. The method of Wyse and Mayall for estimation of density distributions in stellar galaxies from observed rotational velocities was extended to a more realistic model. Methods of calculating pair production or bremsstrahiung cross sections are discussed. The presence of 10 previously unreported gamma rays was observed in the decay of Ag/sup 1//sup 1//sup 3/. The photoproton yield from Be/ sup 9/ was investigated. Theoretical studies … more
Date: September 1, 1960
Item Type: Refine your search to only Report
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Apparatus for Determining Linear Thermal Expansions of Materials in Vacuum or Controlled Atmosphere

Description: An apparatus for determining linear thermal expansion data up to 1350 deg C for materials that cannot be heated in air is described. Expansion is not measured directly, but is derived from the differential expansion between the material being tested and the materials of construction of the dilatometer. The apparatus is calibrated against published data on the linear thermal expansion of both fused silica and polycrystalline tungsten metal. It can be operated either as a high-vacuum or as a cont… more
Date: January 1, 1960
Creator: Fulkerson, S. D.
Item Type: Refine your search to only Report
open access

APPARATUS FOR THE STUDY OF FISSION-GAS RELEASE FROM NEUTRON-ACTIVATED FUELED GRAPHITE

Description: A simple laboratory apparatus for the study of fissiongas release from neutron-activated fueled graphite was developed. Xenon-133 released from a heated specimen is carried in a helium sweep gas to a charcoal trap, where the accumulated activity is monitored continuously by a scintillation detector, ratemeter, and pen recorder. The maximum specimen temperature (2500 deg F) is achieved in 10 min with an induction heater. All instrumentation is commercially available. Data for several neutron-act… more
Date: June 1, 1960
Creator: Rosenberg, H. S.; Lieberman, R.; Sunderman, D. N. & Diethorn, W. S.
Item Type: Refine your search to only Report
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