Air blast studies with animals. Part II. (open access)

Air blast studies with animals. Part II.

Goats under Nembutal and mice were exposed in a shock tube modified to give longer-duration overpressures and equipped with ports for photography. Except for ear damage, displacement still seemed to be the major cause of injury in goats in the 4-foot section of the tube. However, it was found that mice were killed, apparently by pure blast, in a particular position in a particular type of side chamber attached to the higher-pressure, smaller-diameter, section of the tube. The relation between maximum velocity of displacement and the distance animals were thrown was fairly regular. The probability of injury over different terrains is discussed. (auth)
Date: April 1, 1961
Creator: Anderson, R. S.; Stemler, F. W. & Rogers, E. B.
Object Type: Report
System: The UNT Digital Library
PHYSICS ANALYSIS OF PROPOSALS FOR EBWR CORE 2 (open access)

PHYSICS ANALYSIS OF PROPOSALS FOR EBWR CORE 2

Two concepts were investigated as possibilities for the next loading of EBWR. One is a light water spiked plutonium recycle system; the second is a conventional uniformly loaded system with the option of different enrichments in two radial zones. It is concluded that the plutonium recycle scheme is not feasible in EBWR at 100 Mw, and recommendation for a two-enrichment loading for various burnups is made. (auth)
Date: April 1, 1961
Creator: Avery, R. & Kelber, C.N.
Object Type: Report
System: The UNT Digital Library
RECOVERY OF Np-237 BY AN OXIDATION-REDUCTION FLUORIDE PRECIPITATION METHOD (open access)

RECOVERY OF Np-237 BY AN OXIDATION-REDUCTION FLUORIDE PRECIPITATION METHOD

Several hundred grams of Np/sup 237/ in nitric acid solution was approximately 95% recovered as NpO/sub 2/ of >99.5% purity. The remaining 5% was recovered as a nitric acid solution of 99.95% purity. The neptunium was oxidized to the soluble +6 state with sodium bromate, and Pu(IV), thorium, and other impurities in the solution were precipitated as fluorides. The neptuninum was then reduced to Np(IV)) with sulfur dioxide and precipitated as KH/sub p/F/sub 5/ , dissolved in nitric acid, precipitated as neptunium oxalate, and calcined to the oxide. The recovered material balance was 99.91% with a process loss of 0.09%. (auth)
Date: April 1, 1961
Creator: Baybarz, R.D.
Object Type: Report
System: The UNT Digital Library
Gamma-ray scanning techniques for fast breeder reactor safety studies (open access)

Gamma-ray scanning techniques for fast breeder reactor safety studies

A radiation scanning device was constructed to observe meltdown of fast breeder reactor fuel elements in the TREAT reactor by means of self gamma emission. Although the original desired specification was to view natural uranium pins with a space resolution of 0.1 in. and a time resolution of 1 millisecond, the system was designed to give the above space resolution, but the time resolution would be 5 milliseconds or longer depending on the signal intensity. The system failed to give satisfactory pictures because of low signal strength which gave poor contrast against high-strength background from the container required for safety reasons. Measurements indicated that a Mark III system could be constructed to view enriched pins in the standard container with a space resolution of 0.15 in. horizontally and 0.75 in. vertically with a time resolution of 5 milliseconds. (auth)
Date: April 1, 1961
Creator: Beach, L. A.; Pieper, A. G. & Young, M. P.
Object Type: Report
System: The UNT Digital Library
A Geometry Correction for Plane Source Age Measurements in Hydrogenous Media (open access)

A Geometry Correction for Plane Source Age Measurements in Hydrogenous Media

None
Date: April 1, 1961
Creator: Bennett, E. F. & Haugsnes, J.
Object Type: Report
System: The UNT Digital Library
Summary of the Apda Fuel Development Programs (open access)

Summary of the Apda Fuel Development Programs

A summary is presented of the development status, through 1960, of work done on: Core A, the U--10 wt.% Mo fuel and U--3 wt.% Mo blanket, and Core B, the U0/sub 2/--SS cermet and the UO/sub 2/ axial blanket for the Fermi Fast Breeder Reactor; advanced fast reactor fuels; and paste fuels. (B.O.G.)
Date: April 1, 1961
Creator: Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
Object Type: Report
System: The UNT Digital Library
Experimental Evaluation of the Radiation Protection Provided by an Earth- Covered Shelter (open access)

Experimental Evaluation of the Radiation Protection Provided by an Earth- Covered Shelter

against fall-out radiation provided by an earth-covered shelter. The study indicated that the shelter offered excellent protection from fall-out radiation deposited on and around the shelter. This study also added additional data to the research in radiation shielding provided by various structures which is being conducted by the Civil Effects Test Operations, Division of Biology and Medicine, U. S. Atomic Energy Commission. A fall-out radiation field was simulated by pumping, at constant speed, a sealed Co/sup 60/ source through a long length of tubing which was evenly distributed over an area. Radiation measurements were made inside the shelter by dose-integrating ionization chambers. In general, the results indicated that the protection factor (ratio of the open- field exposure dose rate to the exposure dose rate in the structure) was approximately 5000 in the center of the shelter, increasing to 10,000 to 15,000 along the sides, and decreasing to about 3000 near the ends. Directly below vents the protection factor was found to be approximately 2500 at the 3-ft level. The shelter was a halfround corrugated-steel structure covered by a minimum of approximately 2 ft of earth on the top and 5 to 7 ft of earth on the sides. (auth)
Date: April 1, 1961
Creator: Burson, Z. & Borella, H.
Object Type: Report
System: The UNT Digital Library
The Magnetic Properties of Deformed Nuclei (open access)

The Magnetic Properties of Deformed Nuclei

It is shown that the magnetic moments of odd-A deformed nuclei can be interpreted in terms of the independentparticle model with interconfigurational mixing due to the very-short-range residual forces. The latter are implied by using the empirically reduced spin gyromagnetic ratios. The effects of these residual forces on the collective gyromagnetic ratios g/sub R/ are discussed in terms of pair correlation. The effect of particle-rotation interaction on the magnetic moment and the collective gyromagnetic ratio are shown. The g/sub R/ values are obtained from the magnetic moments and the matrix elements for M1 transitions in tais band. It is found that these mechanisms give a satisfactory account of the collective gyromagnetic ratio of Dy/sup 161/, Ho /sup 165/, Er/sup 167/, and Hf/sup 179/. (auth)
Date: April 1, 1961
Creator: Chiao, L.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Response of Dual-Purpose Reinforced-Concrete Mass Shelter (open access)

Response of Dual-Purpose Reinforced-Concrete Mass Shelter

BS>A reinforced-concrete dual-purpose underground parking garage and personnel sheiter designed for a long-duration incident pressure of 40 psi was tested. The sheiter was exposed to shot Priscilla, an approximately 37-kt 700-ft balloon burst (June 24, 1957), at a ground range of 1600 ft (predicted 35-psi peak incident-pressure level). The recorded peak incident pressure at the shelter was approximately 39 psi. Postshot soil borings were made to obtain undisturbed samples for determining soil characteristics. Preshot and postshot field surveys were made to determine the total lateral and vertical displacement of the structure. The test structure provided adequate protection from the effects of the test device at the test GZ distance. Despite failure of the door sealing gasket, a rise in pressure in the interior did not exceed 1.0 psi. The flat-slab roof and supporting structure were more than adequate to resist the 39psi peak incident test loading. (P.C.H.)
Date: April 1, 1961
Creator: Cohen, E.; Laing, E. & Bottenhofer, A.
Object Type: Report
System: The UNT Digital Library
Response of dual-purpose reinforced-concrete mass shelter. Project 30. 2 of Operation Plumbbob (open access)

Response of dual-purpose reinforced-concrete mass shelter. Project 30. 2 of Operation Plumbbob

A reinforced-concrete dual-purpose underground parking garage and personnel shelter designed for a long-duration incident pressure of 40 psi was tested. The shelter was exposed to shot Priscilla, an approx. 37-kt 700-ft balloon burst (June 24, 1957), at a ground range of 1600 ft (predicted 35-psi peak incident-pressure level). The recorded peak incident pressure at the shelter was approximately 39 psi. Postshot soil borings were made to obtain undisturbed samples for determining soil characteristics. Preshot and postshot field surveys were made to determine the total lateral and vertical displacement of the structure. The test structure provided adequate protection from the effects of the test device at the test GZ distance. Despite failure of the door sealing gasket, a rise in pressure in the interior did not exceed 1.0 psi. The flat-slab roof and supporting structure were more than adequate to resist the 39-psi peak incident test loading.
Date: April 1, 1961
Creator: Cohen, E.; Laing, E. & Bottenhofer, A.
Object Type: Report
System: The UNT Digital Library
The H-1 High Temperature Graphite Irradiation Experiment (open access)

The H-1 High Temperature Graphite Irradiation Experiment

A high temperature graphite irradiation experinient was performed in the GETR core to determine the effects of differences in manufacturing, formulation, and graphitization temperatures on radiation-induced eontraction. The experiment was performed at temperatures of 800 to 1200 deg C in an intense fast neutron flux. The maximum integrated exposure of the sample positions was 3.2 x 10?sup 21/ nvt, E> 0.18 Mev, corresponding to approximately 24,000 MWD/AT in a conventional graphite-moderated reactor. All the graphites tested, with the exception of the controls, were needle coke filler, coal tar pitch binder graphites varying mn particle size, graphitization temperature, and impregnation. From theoretical and experitnental considerations, the formulations and treatments were expected to result in a relatively stable graphite in the direction transverse to extrusion. For comparison of the experimental results to existing experience, a conventional graphite, CSF, was used at each irradiation position. The results showed that the graphite most stable to contraction was graphaitized at a high temperature(>3100hC) and made from small particle size (all flour) filler. In all cases, the needle coke graphite contracted at a lower rate than the CSF graphite. Differences attributable to the size of extrusion and/or post graphitization cooling rate were discerned readily. Auxil iary …
Date: April 1, 1961
Creator: Davidson, J. M. & Helm, J. W.
Object Type: Report
System: The UNT Digital Library
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1961 (open access)

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1961

Preparation of a gamma U/sub 3/O/sub 8/ single crystal for x ray examination is reported. Data from developmental work on binary Nb alloys are presented on stresses to produce deformation rates of 0.001, 0.01, and 0.1% per hr at 650, 800, and 1000 deg C. Developmental work on miniature heating elements for use in a power-balancing thermal-neutron flux sensor is reported for imbedded wire and film-conductance elements. In development of Th-- U alloys, chemical analysis data obtained from skull-cast samples are given. Results of a 1-month test on corrosion of Th-base compounds by NaK at 1200 deg F are tabulated. Data are given on mechanical and structural properties of Pu alloys being developed for high temperature propulsion uses. Continued studies of PuO/sub 2/ compatability with various stainless steels are reported. Efforts were devoted to characterizing sintered UO/sub 2/ bodies by quantitative metallography. Techniques were developed for fabrication of cermet fuels containing 80 vol.% UO/ sub 2/ and the remainder metals such as Cr, Mo, Nb or stainless steel. Fabrication studies on UN and UC fuels were conducted along with studies of gas pressure bonding methods. In development of UC, data on U--C systems at 1000 to 1500 deg C were …
Date: April 1, 1961
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Object Type: Report
System: The UNT Digital Library
RADIOLYTIC AND CHEMICAL STABILITY OF PURE HYDROCARBONS (open access)

RADIOLYTIC AND CHEMICAL STABILITY OF PURE HYDROCARBONS

The tendency of various classes of pure hydrocarbons to form zirconium- complexing ligands during chemical or radiolytic degradation was evaluated. Olefins and aromaticcycloparaffins (mixed type) formed the most ligands and normal paraffins the fewest. (auth)
Date: April 1, 1961
Creator: Dennis, B. P.
Object Type: Report
System: The UNT Digital Library
Corrosion of Some Reactor Materials in Dilute Phosphoric Acid (open access)

Corrosion of Some Reactor Materials in Dilute Phosphoric Acid

Corrosion tests in dilute phosphoric acid (pH 3.5) at elevated temperature are described for X8001 aluminum, 18-8 stainless steels, aluminized carbon steel, and Zircaloy. In a 307-day dynamic test at 18 ft/sec and 315 deg C, X8001 aluminum corroded at a rate of 1/2 mdd for the first 240 days. In subsequent exposures, the corrosion rate increased, but the total average penetration at 307 days was only 0.0005 inch. At 200 days, the total corrosion in this test was one-fiftieth that in distilled water. Static tests at 225 deg C gave corrosion rates too low to measure (<0.2 mdd). Of several different 18-8 stainless steels tested in this solution at 315 deg C, only sensitized type 316 suffered intergranular attack. General attack rates of the other samples, of the order of 1/4 mdd, were obtained for the period from 94 to 186 days. Although this is much larger than the rate in distilled water, it represents a penetration rate of only about 5 x 10/sup -//sup 5/ inch/year. Aluminized carbon steel did not suffer rapid corrosion in this solution at 315 deg C, even when large areas of the carbon steel were exposed. There was a tendency for corrosion to …
Date: April 1, 1961
Creator: Draley, J. E.; Greenberg, S. & Ruther, W. E.
Object Type: Report
System: The UNT Digital Library
Corrosion of Aluminum and its Alloys in Superheated Steam (open access)

Corrosion of Aluminum and its Alloys in Superheated Steam

The corrosion behavior of pure aluminum and some of its alloys in superheated steam was found to depend markedly on the method of starting the corrosion test. Pure aluminum samples survived only in tests that were brought to temperature and pressure very rapidly. Resistant Al-- Ni-- Fe alloys performed well only if a relatively slow starting procedure was used, suffering extensive blistering or complete disintegration in a test started rapidly. Over the range of temperature and pressure investigated, 400 to 540 deg C and 150 to 600 psig, with optimum starting conditions both pure aluminum and resistant Al-- Ni-- Fe alloy samples quickly formed a very protective oxide film. Interference colors were noted for exposures of several weeks. Samples surviving a 260-day test at 540 deg C and 600 psig had less than 1-mg/cm/sup 2/ weight gain. Nonresistant alloys disintegrated in short corrosion exposures. A penetrating attack, initiated in only a few spots, rapidly destroyed the samples. The effects of composition, dispersion of second-phsse compounds, hydrogen porosity, and pretreatments were investigated for 5.6% Ni--0.3% Fe-0.1% Ti in 540 deg C, 600-psig steam. It was concluded that porosity produced by corrosion product hydrogen was a major factor in the survival of …
Date: April 1, 1961
Creator: Draley, J. E.; Ruther, W. E. & Greenberg, S.
Object Type: Report
System: The UNT Digital Library
Radioactivity Dissemination Near Uranium Processing Mills (open access)

Radioactivity Dissemination Near Uranium Processing Mills

This report follows a preliminary survey made to study radioactive contamination of the soil (and to some extent in the air and waters) in the vicinity of seven uranium processing mills.
Date: April 1, 1961
Creator: Feldman, M. H.; Troianello, Emilio J.; Coates, G. K. & Sheehan, W. R.
Object Type: Report
System: The UNT Digital Library
ELECTRON POLARIZATION OPERATORS (open access)

ELECTRON POLARIZATION OPERATORS

Two types of electron polarization operators are surveyed. A three- vector operator is described that is appropriate for calculations involving plane- wave states. A four-vector operator is described that can be used for taking account of external electromagnetic fields. (T.F.H.)
Date: April 1, 1961
Creator: Fradkin, D.M. & Good, R.H. Jr.
Object Type: Article
System: The UNT Digital Library
Irradiation testing of tubular fuel elements: PT-IP 292A. Final report (open access)

Irradiation testing of tubular fuel elements: PT-IP 292A. Final report

This report discusses Zircaloy-2 clad uranium and uranium-2 weight percent zirconium fuel tubes which were irradiated to 3200 MWD/T in a high temperature water cooled loop. The outer clad of one tube split due to swelling of the uranium. Postirradiation examination of the fuel cores included metallography, electron microscopy, density determinations, dimensional measurements, and radiochemical burn-up analysis.
Date: April 1, 1961
Creator: Geering, G. T.
Object Type: Report
System: The UNT Digital Library
Annual Report of the Girl Scouts of the United States of America: 1960 (open access)

Annual Report of the Girl Scouts of the United States of America: 1960

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1960, activities, finance, statistics, organizational leadership, and other information about scouting programs.
Date: April 1, 1961
Creator: Girl Scouts of the United States of America
Object Type: Report
System: The Portal to Texas History
Comparative Boron Isotopic Analysis (open access)

Comparative Boron Isotopic Analysis

S>Surface ionization results for natural boron isotopic analysis are in agreement with other recent investigations indicating a B/sup 11//B/sup 10/ atom ratio nesrer to 4.00 than the more commonly accepted value of 4.31 based on BF/ sub 3/ analysis. (auth)
Date: April 1, 1961
Creator: Goris, P.; Morgan, T. D. & Nielsen, R. A.
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 1, 1961 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 1, 1961

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Object Type: Report
System: The UNT Digital Library
FILM GROWTH ON ALUMINUM IN HIGH-TEMPERATURE WATER (open access)

FILM GROWTH ON ALUMINUM IN HIGH-TEMPERATURE WATER

Film growths on aluminum and two aluminum-1 wt.% nickel alloys in water at 250 and 350 deg C were studied. It was found that oxide growth does not advance on a uniform front but, to the contrary, the advancing surface contains many outcrops in the form of thin platelets, chunky outcrops, and whiskers. With both the pure metal and the alloys considerable intergranular attack was observed. The general corrosion product was usually more uniform in crystal size when formed on the pure metal, but variations in crystal size were observed on both aluminum and alloys with varying features of the metal surface. The roughness of the general oxide surface (includlng outcrops) was found to increase rapidly to about 0.2 micron and then remain relatively constant with increasing film thickness. The composition of films formed under all investigated conditions, except one, was found to be boehmite ( alpha -Al/sub 2/O/sub 3/- H/sub 2/O). This exception was films carried by the alloy specimens after testing for 32 days at 350 deg C. In this case the main corrosion film was still boehmite, but in addition the outer surface supported long needles of diaspore ( beta -Al/sub 2/ O/sub 3/- H/sub 2/O). (auth)
Date: April 1, 1961
Creator: Hart, R.K. & Ruther, W.E.
Object Type: Report
System: The UNT Digital Library
Results of the 105-DR effluent piping stress measurements from IP-342-AG (open access)

Results of the 105-DR effluent piping stress measurements from IP-342-AG

Development Test IP-342-AG was run on August 12, 1960, and August 25, 1960, for the purpose of measuring temperatures, pressures and strains throughout the 105-DR effluent systems. On October 24, 1960, additional strain readings were recorded prior to reactor shutdown, thus yielding strain data virtually free from strain gage drift. Results of the tests were analyzed to determine if sustained operation at 93{degree}C--95{degree}C bulk outlet temperature is practical, without increasing the danger of effluent system failure. This document presents the results of stress measurements made during the test and their significance relevant to operation at 93--97{degree}C bulk outlet temperature. Strain measurements were made by R. L. Loundagin of Materials Development, Equipment Development Operation, and by Radiographics Testing Operation, Hanford Laboratories Operation. A sketch showing the strain gage locations is included.
Date: April 1, 1961
Creator: Hawley, J. P. & Adams, O. E. Jr.
Object Type: Report
System: The UNT Digital Library
High Power Density Development Project Fourth Quarterly Progress Report : January - March 1961 (open access)

High Power Density Development Project Fourth Quarterly Progress Report : January - March 1961

The fourth quarter of effort applied to the Consumers R & D Program is summarized in the following: high power density fuel development, fuel fabrication development, stability, heat transfer and fluid flow, physics development, operation planning and test coordination.
Date: April 1, 1961
Creator: Holland, L. K.
Object Type: Report
System: The UNT Digital Library