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Analysis of Fuel Element Core Blanks for Argonne Low Power Reactor by Gamma Counting
A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)
Date:
December 1, 1959
Creator:
McGonnagle, W. J. & Perry, R. B.
Object Type:
Report
System:
The UNT Digital Library
Atmospheric Signals From Explosions and Their Interpretation
Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It is concluded that the blast phenomenology of high-altitude shots can be predicted by using modified Sach's scaling. With some extrapolation to the height-of-burst versus blast-yield curve, it should be possible to make order-of-magnitude predictions of blast effects from high-altitude shots up to heights of burst of 1,000,000 ft. (C.H.)
Date:
December 1, 1959
Creator:
Reed, J. W.
Object Type:
Report
System:
The UNT Digital Library
Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels
A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date:
December 1, 1959
Creator:
Goffard, J. W.
Object Type:
Report
System:
The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMI-ANNUAL REPORT FOR JULY THROUGH DECEMBER 1958
Progress is reported in the following studies: the control of a scabies- like mange of rats and pinworms in mice; in vivo measurement of Sr/sup 90/ in dogs; the effects of the chronic ingestion of Sr/sup 90/ in mice; investigation of the tritium labeling of organic compounds by the self-irradiation method; the delayed effects of x irradiation in chickens; development of a new method for the assay of enzymatic activity of various homocysteine transmethylases; the use of a punched-card system for the location of filed prints of electron micrographs; the specific chromosomal control of the mass of the nucleolus and of the cytoplasm in plants; the effect of deuterium oxide on peripheral blood cells in rats; spermatogenesis in irradiated mice; the development of mathematical models for the maintenance and regulation of populations of blood cells of both erythroid and myeloid origin; the effect of boron on the uptake of iron, copper, manganese, and molybdenum in a monocatyledonous plant, the grass Setaria spacelata;, the photoperiodic behavior of sunflowers; the morphology of the mitotic spindle and chromosomes as seen under the interference microscope; the thirty-day survival of female mice and rats given single whole-body exposures to fission neutrons; the effectiveness of combined …
Date:
December 1, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Biological Effects of Radiation, and Related Biochemical and Physical Studies : Semiannual Progress Report [for] Period May 1, 1959 - October 31, 1959
Progress reports from four divisions are included: (1) Division of Biophysics; (2) Division of Clinical Investigation; (3) Division of Nucleoprotein Chemistry; and (4) Radiochemistry Section.
Date:
December 1, 1959
Creator:
Denues, Arthur Russell Taylor, 1914-
Object Type:
Report
System:
The UNT Digital Library
Casting and Fabrication of Core Material for Argonne Low Power Reactor Fuel Elements
The manufacture of fuel blanks used in the fabrication of fuel elements for the Argonne Low Power Reactor is described. The thin, plate-type elements contain a wrought aluminum-base core alloy with a nominal composition of 17.5 wt.% enriched uranium, 2.0 wt.% nickel, and 0.5 wt.% iron, clad with an aluminum-- nickel alloy. The fuel ele ments were fabricated by a picture-frame technique, employing elemental silicon bonding and followed by hot and cold rolling to size. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed. A description of the nondestructive testing method and an evaluation of the manufacturing processes are given. (auth)
Date:
December 1, 1959
Creator:
Salley, R. L. & Burt, W. R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Chariot Project, Phase 2. Preliminary Evaluation Report
None
Date:
December 1, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Comments on Equipment for a PRTR Water Quality Control Laboratory
This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
Date:
December 1, 1959
Creator:
Anderson, H. J. & Peray, R. E.
Object Type:
Report
System:
The UNT Digital Library
CONTROL OF OXYGEN CONCENTRATION IN A LARGE SODIUM SYSTEM
Data on the performances of two types of cold traps in the 50,000-lb radioactive sodium system at the SRE are tabulated. The rates were determined when trap inlet oxygen concentrations were at 8 to 10 parts per million. Oxygen concentration was readily controlled to 8 ppm using a cold trap. Extraction of oxygen from sodium by zirconium at 1200 deg F (hot trapping) reduces the concentration below the limit of detection, i.e., oxide solubility saturation temperature below 225 deg F. The theoretical limit for the equilibrium oxygen concentration was calculated to be less than 7 x 10/sup -6/ ppm. The observed extraction rate of 0.009 lb oxygen/hr was one-half of the rate predicted from material behavior studies. (auth)
Date:
December 1, 1959
Creator:
Hinze, R B
Object Type:
Report
System:
The UNT Digital Library
Corrosion of Stainless Steel in Thorex Process Solutions
The corrosion of 304L and 309SCb stainless steel was studied in HF--HNO/ sub 3/ solutions proposed for the Thorex process. Except for the dissolving and waste evaporation steps in the Thorex process, corrosion of 304L and 309SCb is not expected to exceed that experienced in the Purex process. To minimize the high initial corrosion rate of 309SCb in the boiling HF-- HNO/sub 3/ dissolving solution, a heel of thorium should be maintained in the dissolver. The corrosion rate of 304L in the low activity waste evaporator can be reduced by adding one mole of aluminum per mole of fluoride to the evaporator feed. (auth)
Date:
December 1, 1959
Creator:
Kranzlein, P. M.
Object Type:
Report
System:
The UNT Digital Library
A Dimensional Analysis of the Departure From Nucleate Boiling Heat Flux in Forced Convection
None
Date:
December 1, 1959
Creator:
Griffith, P.
Object Type:
Report
System:
The UNT Digital Library
Experimental Organic Cooled Reactor : Conceptual Design
Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date:
December 1, 1959
Creator:
Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
Object Type:
Report
System:
The UNT Digital Library
FABRICATION OF ALUMINUM-PLUTONIUM ALLOY FUEL ELEMENTS BY COEXTRUSION
The development of the fabrication process and preparation of 144 coextruded fuel elements for the TransPlutonium Program are described. The fuel elements were in the form of coextruded rods, 0.94 in. in diameter and 60 in. in length. The cladding was aluminum (X-8001 alloy) and was 0.040 to 0.120 in. thick. The fuel cores were aluminum-7.35 wt.% plutonium alloy. The fuel elements were coextruded in an extrusion press which was mounted in a plutonium- contaminated glove box. The extruded elements were easily decontaminated. The cast fuel cores for the coextrusion billets were machined only on one end. The fuel elements are currently under irradiation. (auth)
Date:
December 1, 1959
Creator:
Bailey, W.J.; Bloomster, C.H.; Katayama, Y.B. & Ross, W.T.
Object Type:
Report
System:
The UNT Digital Library
FABRICATION OF URANIUM OXIDE FUEL ELEMENTS
The fabrication of UO/sub 2/ fuel elements clad in metallic sheaths by swaging, rolling, and coextrusion was investigated. The effects of the type of UO/sub 2/ and of the materials and dimensions of the sheath were investigated. Fused UO/sub 2/ swaged in stairless-steel tubing reached a maximum density of 93% of theoretical. (auth)
Date:
December 1, 1959
Creator:
Cole, G.R.; Ferrara, A.S. & Kranzlein, H.H.
Object Type:
Report
System:
The UNT Digital Library
GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959
; D = > 6 ; : 6 < 7 8 9 7 9sion theory calculation of the power-density distribution in the EGCR was made in order to reduce the uncertainties in the results of previous calculations. A comparison was made of calculated neutron flux distributions in seven-rod fuel clusters and the preliminary results obtained in the Physical Constants Test Reactor at Harford. Neutron flux ratios for the EGCR lattice cell were calculated for fuel enrichments of 2.0 and 2.6%. Studies were made of the power densities attainable in gas-cooled reactors operated with ceramic material as both fuel and moderator. Extensive studies were conducted to determine how the multiplication factor of a gas-cooled reactor varies with the number of rods in the fuel element cluster, cladding thickness, cladding material, inter-rod spacing, lattice pitch, solid and cored rods, fuel enrichment, and fuel-tomoderator ratio. Reactor Design Studiesi A theoretical study is being conducted of the deflections and stresses in fuel element cladding based on arbitrary temperature distributions. Tests were run to determine the load-carrying ability of the threaded-pin-type graphite column joints proposed for the EGCR. A test program was initiated for studying the behavior of metal-clad graphite bodies. An analytical model for …
Date:
December 1, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR NOVEMBER 1959
At the end of November, 20% of the construction and 80% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Proof testing of various seals and mechanisms for the HWCTR continued satisfatorily. Further analyses are given of the transient behavior of the HWCTR isolated coolant loops and of the experimental data on the nuclear effects of hot moderator. The results of additional fabrication and irradiation tests of uranium metal and uranium oxide are recorded. The manufacture of tubular metallurgical joints between Zircaloy and stainless steel is also reported. (See also DP-415.) (auth)
Date:
December 1, 1959
Creator:
Hood, R.R. & Isakoff, L. comps.
Object Type:
Report
System:
The UNT Digital Library
INITIAL TESTING AND OPERATION OF THE ARGONNE LOW POWER REACTOR (ALPR)
The major events of a program designed to test and operate the completed reactor power plant and associated equipment are described. The design and construction phases of the project, component installation, preliminary systems testing, zero-power experiments, areas affected by the design parameters, reactor operation, plant safety, and reactor operator training are covered. (W.D.M.)
Date:
December 1, 1959
Creator:
Hamer, E.E. ed.
Object Type:
Report
System:
The UNT Digital Library
Logarithms of Factorials From 1 to 2000
A table of logaritams, to the base 10, of factorial n is given for values of n = 1(1)2000 to 15 decimal places. (auth)
Date:
December 1, 1959
Creator:
Owen, D. B. & Williams, C. M.
Object Type:
Report
System:
The UNT Digital Library
MECHANICAL PROPERTY AND FORMABILITY STUDIES ON UNALLOYED PLUTONIUM
The effect of temperature and testing speed on the tension and compression properties of unalloyed plutouium was studied in the alpha , beta , gamma , and delta phases. Compressive formability data were obtained for a load of 100,000 lbs in the aforementioned phases. In addition, preliminary creep, tension impact, and torsion data for alpha -phase plutonium are reported. Extrusion constants and pressures for the beta , gamma , and delta phases were obtained. The roomtemperature tension and compression properties of the beta - and #gg-extruded plutonium were determined. Metallo graphic studies were made to determine the effect of tension, compression, and extrusion, in the indicated phases, on the microstructure of as-cast plutonium. (auth)
Date:
December 1, 1959
Creator:
Gardner, H.R. & Mann, I.B.
Object Type:
Report
System:
The UNT Digital Library
METALLURGICAL STUDIES OF NIOBIUM-URANIUM ALLOYS
In a continuing program, fabrication characteristics, physical and mechanical properties, and corrosion behavior in air, CO/sub 2/, NaK, water, and steam were studied for . binary niobium fuel alloys containing 10, 20, 30, 40, 50, and 60 wt.% uranium To evaluate the effects of two major impurities of niobium, oxygen, and zirconium, three niobium base stocks, differing according to the level of these impurities, were used for each alloy. The impurity combinations employed were 600 ppm oxygen and 0.74 wt.% zirconium, 700 ppm oxygen, and 0.17 wt.% zirconium, and 300 ppm oxygen and 0.02 wt.% zirconium, Representative specimens of these alloys retained their hardness up to 900 deg C The 10 and 20 wt.% uraniuin alloys were successfully rorged at 2500 deg F and rolled at 1800 deg F to sheet. Fabrication characteristics of the remaining alloys are under investigation. The 0.2% offset yield strength of the 10 wt.% uranium alloy was 57,200 psi at room temperature and 36,900 psi at 1600 deg F. For the 20 wt.% uranium alloy it was 93,200 psi at room temperature and 71.000 psi at 1600 deg F. The corrosion life of all of the alloys in air at 572 deg F and in …
Date:
December 1, 1959
Creator:
DeMastry, J. A.; Shober, F. R. & Dickerson, R. F.
Object Type:
Report
System:
The UNT Digital Library
MODERATOR TEMPERATURE COEFFICIENTS IN HEAVY WATER REACTORS
Reactors that are moderated with heavy water differ from those that are moderated with graphite in that (1) the moderator temperature is lower than it may be in graphite reactors, (2) when the moderator temperature is raised, the moderator-to-fuel ratio decreases, and (3) circulation in the moderator introduces local, random changes in reactivity that distort the flux distribution. The large negative contributions to the moderator temperature coefficient from leakage and resonance capture overshadow any positive contribution from eta that may accompany the buildup of plutonium with exposure. The effect of the coefficient on reactor safety depends upon the manner in which the D/sub 2/O circulation couples the reactor power to the moderator temperature. (auth)
Date:
December 1, 1959
Creator:
St. John, D.S.
Object Type:
Report
System:
The UNT Digital Library
A MONTE CARLO CODE FOR THE TRANSPORT OF NEUTRONS
A Monte Carlo code for the BM 704 computer was written to study the transport of neutrons in a uniform heterogeneous lattice of cylindrical fuel assemblies. Models of the geometric and physical processes are used to obtain the neutron age and migration area; the flux as a function of position, energy, and direction; and absorption data from which thermal utilization and the multiplication constant k may be calculated. (auth)
Date:
December 1, 1959
Creator:
Baxter, William V.
Object Type:
Report
System:
The UNT Digital Library
NEUTRON MODERATION BY ACOUSTIC MODES OF METAL HYDRIDES
>The excitation by nuclear collisions of the acoustic modes of a metal hydride crystal was investigated, using a model of the crystal based on experiments on ZrH/sub 2/, but slightly more general. It is found that these modes contribute little tc neutron moderation in ZrH/sub 2/. In the course of the discussion, a generalized form of the Wilkins equation, which determines the spectrum of neutrons thermalizing in a heavy moderator, is developed, applicable when the scattering cross section varies with energy. (auth)
Date:
December 1, 1959
Creator:
Vaughan, E.U.
Object Type:
Report
System:
The UNT Digital Library
NON-PRODUCTION FUELS REPROCESSING, CENTRIFUGATION STUDIES ON VARIOUS DISSOLVER EFFLUENT SOLUTIONS
>The proposed flowsheets for reprocessing of nonproduction fuels include centrifugal separation of particulate matter from various dissolver effluent solutions. The settling characteristics of process solids were determined in water and in cold process solutions. Uranium dioxide particles will be recovered from Zirflex and Sulfex cladding waste solutions, and core-dissolver solutions will be centrifuged for removal of ZrO/sub 2/, metallic slimes, siliceous matter, and uranium-bearing solids. (W.L.H.)
Date:
December 1, 1959
Creator:
Amos, L.C.
Object Type:
Report
System:
The UNT Digital Library