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Uses of Advanced Pulsed Neutron Sources. Report of a Workshop Held at Argonne National Laboratory, October 21-24, 1975

Description: This report contains the conclusions that were drawn by nine panels of scientists in the fields of Biology; Chemical Spectroscopy; Chemical Structures of Crystalline Solids; Chemical Structures of Disordered Solids and Inhomogeneous Systems; Dynamics of Solids, Liquids, Glasses, and Gases; Magnetism; Neutron Sources; and Radiation Effects. The nine panel reports describe the applications found in these scientific areas, accompanying them with conceptual instruments designed for the measurements and with calculations to establish feasibility.
Date: 1976?
Creator: Carpenter, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois

Description: Papers presented at the third Post-Accident Heat Removal Information Exchange concerning heat distribution and criticality considerations, particulate-bed phenomena, pool heat transfer and melt-front phenomena, behavior of heated concrete and sodium-concrete interactions, design-related studies, gas bubbling and boiling effects, and materials interactions at high temperatures and experimental methods.
Date: 1978?
Creator: Baker, Louis, Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report. October 1 - December 31, 2010.

Description: Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near-real time. Raw and processed data are then sent approximately daily to the ARM Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998. The U.S. Department of Energy (DOE) requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1 - (ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the first quarter of FY2010 for the Southern Great Plains (SGP) site is 2097.60 hours (0.95 x 2208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1987.20 hours (0.90 x 2208) and for the Tropical Western Pacific (TWP) locale is 1876.80 hours (0.85 x 2208). The first ARM Mobile Facility (AMF1) deployment in Graciosa Island, the Azores, Portugal, continued through this quarter, so the OPSMAX time this quarter is 2097.60 hours (0.95 x 2208). The second ARM Mobile Facility (AMF2) began deployment this quarter to Steamboat Springs, Colorado. The experiment officially began November 15, but most of the instruments were up and running by November 1. Therefore, the OPSMAX time for the AMF2 was 1390.80 hours (.95 x 1464 hours) for November and December (61 days). The differences in OPSMAX performance ...
Date: February 1, 2011
Creator: Sisterson, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

APPLIED MATHEMATICS DIVISION SUMMARY REPORT FOR JULY 1, 1959 THROUGH JUNE 30, 1960

Description: A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)
Date: October 31, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

APPLIED MATHEMATICS DIVISION SUMMARY REPORT, JULY 1, 1962 THROUGH JUNE 30, 1963

Description: Summaries of the computer programs initiated or modified are listed, and the programs developed for the GUS digital computer complex are described. Information included in bulletins or newsletters on computers is indicated, and the new routines for the IBM-704, IBM-1401, and GEORGE are listed. The computer equipment (including GEORGE) presently available for computations is briefly described. An automatic data processing system (CHLOE) was developed for spark chamber photograph analysis. It uses a fiber optics cathode ray tube scanner and an ASI-210 digital computer. (D.C.W.)
Date: October 31, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

SYMPOSIUM ON PHYSICS AND NONDESTRUCTIVE TESTING, HELD AT ARGONNE NATIONAL LABORATORY, OCTOBER 4-5, 1960

Description: BS>Twelve papers are included which were presented at the Symposium on Physics and Nondestructive Testing. The subject matter of the papers include neutron radiography, elastic waves, ultrasonic waves, magnetic properties, applied mathematics, and accelerator applications. Separate abstracts have been prepared for eleven papers, while the remaining paper was previously abstracted in NSA. (D.L.C.)
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

RADIOLOGICAL PHYSICS DIVISION SEMIANNUAL REPORT, JULY THROUGH DECEMBER 1960

Description: Data are presented from studies on the total Ra>s2/sup >> /ntent, radon retention, and activity of hotspots in human bones approximately 30 yr post- adiministration of Ra. Preliminary results are reported from a study of the incidence of bone tumors following injection of Pu>s2/sup >>,/a>s2/sup >>/ / sup ,/r>s9/sup >,/r Ca>s4/sup > / mice. Calculations were made of the radiation dose from hotspots formed in bone by these radioisotopes. The gamma spectra of 20 subjects who contained known quantities of K>s4/sup > /re obtained with several different sized NaI(Tl) crystals located at various points around the body. These spectra were analyzed to determine the variations in counting rates that resulted with each patient-crystal arrangement. The total-body gamma spectra of 12 unexposed employees were measured with the human spectrometer over a span of 30 mo. Data are tabulated on Co>s1/sup >>//s4/sup > /tios. The respo nse of a scintillation counter to gamma radiation asAa function of incidence angle was measured. Studies were made on the refractive index of selected optical media. Improvements were made in the design and in the scintillator solvent for a twin scintillation fast neutron detector. Measurements were made of the skeletal and soft tissue content of Ra in normal humans whose primary source of Ra was food. Calculations of the half lives and distributions of stuble Pb and Pb>s2/sup >> / the human body are discussed. Meteorological studies reported include a comparison of observed plume rise of stack effluent with values obtuined from well-known formulas, towing tank studies of horizontal turbulent air flow, and soil temperature studies. (C.H.)
Date: February 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, JUNE 1960

Description: 7 9 7 D 8 8 9 9 7 7 ; 8 < fuel-reprocessing plant using pyrometallurgical procedures is being designed and constructed as part of the Experimental Breeder Reactor No. 2 project. Cable samples sealed with Temporell No. 741 were irradiated to 3.0 x lO/sup 9/ rad. Tests of the absorber-type fume trap were successful. Preparations were continued for high- activitylevel demonstrations of the melt-refining process for EBR-2 core fuel. An attractive and efficient procedure for removing uranium skull material from a melt-refining crucible is to convent it to free-flowing oxide powder by oxidation with a dilute oxygen- argon mixture at 700 to 800 deg C. Two complete runs were made for both demonstrating and pin-pointing difficulties in the drag-out or skullreclamation process. Investigation of the reduction of uranium oxides by liquid magnesium alloys was continued. Two runs were made to demonstrate recovery of plutonium from a magnesium solution by distillation of the magnesium. Operation of a mild steel corrosion loop for circulating a U-Mg- Cd alloy at 550 deg C was terminated after 4800 hr of trouble-free operation. The solubility of titanium in liquid cadmium was found to vary between 0.047 at.% at 449 deg C to 0.15 at. % at 651 deg C. The solubility of uranium in liquid lead over the temperature range from 415 to 802 deg C is given. The solubility of uranium in cadmium-magnesium solutions containing up to 72 wt.% Mg at 6l0 deg C was found to decrease smoothly from about 2 wt.% in pure cadmium to about 0.002% in72 wt.% Mg. The partition coefficients of a number of representative fissile and fission product elements between the immiscible liquids aluminum and cadmium at 680 to 688 deg C were measured. The heat of combustion of tungsten disulfide in oxygen was determined to ...
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1960

Description: Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg C has been in trouble-free operation for 3000 hrs. Recovery of Pu from Mg solution by distillation of Mg was demonstrated on 1-g Pu scale. The solubility of Th in liquid Cd was measured over the temperature range from 1.9 x 10/sup -3/ per cent at 348 deg C to 1.8 x 10/sup -2/ per cent at 658 deg C. The solubility of Mn in liquid Cd was found to range from 0.27% at 414 deg C to 1.43% at 661 deg C. The solubility of Ni in liquid Cd was measured. The partition of U between liquid Al and liquid Cd was studied as a function of U concentration. The reaction of Al with a liquid Cd solution containing U, Zr, and Ce was studied. The free energy of formation of the U--Pb intermetallic compound UPb/sup 3/ was measured between 374 and 846 deg C by means of a galvanic cell method. Magnetic susceptibility measurements on the intermetallic comPound CeCd/sub 11/ were made over a range of temperature from 4 to 295 deg K. Fuel Cycle Applications of Volatility and Fluidization Techniques. The Direct Fluorination Process is currently aimed toward the processing of the Zircaloyclad, UO/sub 2/ fuel typical of the Dresden Reactor. The direct fluorination of dense UO/sub 2/ pellets submerged in an inert fluidized medium was carried ...
Date: October 31, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, AND DECEMBER 1956

Description: A study of mass transfer in a continuous-flow mixing chamber, fluoride volatilization separations process, corrosion testing in fused fluoride systems, behavior of Pu during volatilization of UF/sub 6/, preparation of PuF/sub 6/ by fluorination of PuF/sub 4/, particle size distribution and U content of UF/sub 4/ , stoichiometric behavior of the reaction IF/sub 5/ + F/sub 2/ + I/sub ignition data on stainless steel, were reported. Studies were continued on the analysis of crude green salt from U ore concentrates, fluidized-bed green salt pilot plant, calcination of reactor fuel wastes, reactor chemistry, chemical- metallurgical separation processes, waste processing operations, and the operation of the gammairradiation facility. (W.L.H.)
Date: March 1, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, DECEMBER 1959

Description: Chemical-Metallurgical Processing. A direct-cycle pyrometallurgical fuel-processing plant is being constructed in conjunction with EBR-II. The gamma- irradiation testing of the 175-watt white fluorescent mercury vapor lamp was continued to an integrated exposure of 2 x 10/sup 9/ rad. Irradiation tests of Shell APL grease were completed, and the estimated useful life of this grease in the Air and Argon Cells is 2 and 3 years, respectively. Tests of the three - types of d-c motors used in the operating manipulator of the Argon Cell indicate an expected useful cell operating life of 2 to 3 years. Continued irradiation tests of mineralinsulated cable show no catastrophic breakdown of the electric insulation even after an accumulated gamma dose of 8.4 x 10/sup 9/ rad. The scheme currently under consideration for processing melt-refining residues involves a reduction of skull oxides by a solution of Mg in liquid Cd. Molten salt fluxes had variable effects on the rate of oxide reduction in dilute Mg systems. Work was continued on development of processes for EBR-II blanket materials. A large-scale metal-distillation unit to demonstrate metal distillation at rates up to 100 kg/hour is under construction. Two medium carbon steel thermal-convection loops were built and operated to ascertain the extent of corrosion under adverse thermal conditions. Data were obtained for the solubilities of V, Fe, and Ni in liquid Cd at temperatures from 400 to 650 deg C. Corrections were made to data on the solubility of Th in liquid Zn. Solubilities of U in Si-free Zn--Mg solutions were found to be significantly higher than when silicon was present. The peritectic temperature in the U--Cd system was found to be 474 plus or minus l deg C. The activity coefficient of U in Al at4.8% U and 686 deg C is estimated to be 1.25 x 10/sup ...
Date: February 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY, FEBRUARY, MARCH 1961

Description: 8 7 < 6 ; : : = 8 g developed for recovering fissionable and fertile materials from shortcooled reactor fuels. The second laboratory demonstration of the melt-refining process with highly irradiated EBR- IItype fuel pins was completed. A 392-g charge of U-5% fissium fuel pins irradiated to an estimated burnup of 0.4 total at.% and cooled 28 days was melt refined for three hours at 1400 deg C. Data were not obtained on the behavior of fission products. The effect of N concentration on the nitridation rates of unirradiated U-fissium alloys in Ar-N atmospheres was determined. Experiments on the storage of fuel pins at 350 deg C in Ar atmospheres showed that the presence of 5% N lowered product yields only slightly during subsequent melt-refining operations. Supplementary pouring techniques, such as the use of probes and mashers designed to break crusts over the melts, are moderately effective, but are a less desirable solution to the problem of maintaining high yields than the elimination of contaminants in the Ar atmosphere. A liquid metal process is under development for recovery of the fissionable material contained in melt refining crucible skulls produced in the EBR-II fuel cycle. Information obtained in separate studies of the individual process steps is listed. A systematic study is underway to ascertain the influence of atomic size, metallic valence, and electronic configuration on the coprecipitation of various metallic elements with the Cd-Ce intermetallic phase CeCd/sub 11/. Values for the coprecipitation coefficient lambda , defined by the equation log (tracer in solution/ total tracer) = lambda log (carrier in solution/total carrier), were determined for Na, Li, K, Y, Ba, lambda = 0; La, lambda = 1.49; Th, lambda = 1.08; Pr, lambda = 0.63; Ga, lambda = 0.23; Sm, lambda = 0.17; U, lambda = 0.13; Sr, lambda = ...
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, OCTOBER, NOVEMBER, DECEMBER 1960

Description: Chemical-metallurgical processing studies were made of pyrometallurgical development snd research, and fuel processing facilities for EBR-II. Fuel-cycle applications of fluidization and volatility techniques included laboratory investigations of fluoride volatility processes, engineeringscale development, and conversion of UF/sub 6/ to UO/sub 2/. Reactor safety studies consisted of metal oxidation and ignition kinetics, and metal-water reactions. Reactor chemistry investigations were conducted to determine nuclear constants and suitable reactor decontamination methods. Routine operations are summarized for the high-level gammairradiation facillty and waste processing. (B.O.G.)
Date: March 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

METALLURGY DIVISION ANNUAL REPORT FOR 1959

Description: Engineering Metallurgy. Investigations were made on the following: development programs for Experimental Breeder Reactor No. 2 (EBR-II); fabrication of care and blanket components for Argonne Fast Source Reactor (AFSR); fabrication of spiked fuel rods for Experimental Boiling Water Reactor (EBWR) (Core lA); fuel for Transient Test Reactor Facility (TREAT); fuel elements for Experimental Breeder Reactor No. 1 (EBR-I) (Mark-IV); canning of plutonium loading for Zero Power Reactor No. 3 (ZPR-III); development of ceramic fuel materials; irradiation evaluations of various experimental fuel and control-rod materials: postirradiation examinations of full-scale reactor fuel elements: development of corrosion-resistant fuel and jacketing materials; nondestructive testing developments; and metallurgical assistance to the Fast Reactor Safety Program. Basic Metallurgy. Investigations were made on the following: preparation of high-purity materials; physical metallurgy of uranium; constitution and properties of uranium and plutonium alloys; alloying properties; x-ray and neutron-diffraction studies; problems in metal physics; corrosion research; irradiation effects; and ceramicmaterials research. (W.L.H.)
Date: October 31, 1960
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Partner: UNT Libraries Government Documents Department

USERDA computer program summaries. Numbers 177--239

Description: Since 1960 the Argonne Code Center has served as a U. S. Atomic Energy Commission information center for computer programs developed and used primarily for the solution of problems in nuclear physics, reactor design, reactor engineering and operation. The Center, through a network of registered installations, collects, validates, maintains, and distributes a library of these computer programs and publishes a compilation of abstracts describing them. In 1972 the scope of the Center's activities was officially expanded to include computer programs developed in all of the U. S. Atomic Energy Commission program areas and the compilation and publication of this report. The Computer Program Summary report contains summaries of computer programs at the specification stage, under development, being checked out, in use, or available at ERDA offices, laboratories, and contractor installations. Programs are divided into the following categories: cross section and resonance integral calculations; spectrum calculations, generation of group constants, lattice and cell problems; static design studies; depletion, fuel management, cost analysis, and reactor economics; space-independent kinetics; space--time kinetics, coupled neutronics-- hydrodynamics--thermodynamics and excursion simulations; radiological safety, hazard and accident analysis; heat transfer and fluid flow; deformation and stress distribution computations, structural analysis and engineering design studies; gamma heating and shield design programs; reactor systems analysis; data preparation; data management; subsidiary calculations; experimental data processing; general mathematical and computing system routines; materials; environmental and earth sciences; space sciences; electronics and engineering equipment; chemistry; particle accelerators and high-voltage machines; physics; controlled thermonuclear research; biology and medicine; and data. (RWR)
Date: October 1, 1975
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Partner: UNT Libraries Government Documents Department