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Serial/Series Title
Atomic Energy Commission Reports
264
University of California Radiation Laboratory Reports
112
HW (Series)
110
Hanford Works Reports
103
AEC research and development report
91
Oak Ridge National Laboratory Reports
76
TID
60
NYO (Series) (New York)
49
Report (U.S. Atomic Energy Commission)
43
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Research on Krypton 85 : Seventh Monthly Progress Report Covering December 1, 1959 to December 31, 1959
Work during this report period includes a continuation of the study of the effect of krypton 85 on the polymerization of styrene; an attempt at evaluation of the polymers produced; and the effect of krypton radiation on the electrical properties of gases, such as the rare gases, and nitrogen, and oxygen. the results obtained are summarized in the report.
Date:
January 21, 1960
Creator:
Miller, H. S.; Marancik, W. G. & Zufall, J.
Object Type:
Report
System:
The UNT Digital Library
Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959
The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date:
January 15, 1960
Creator:
Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Object Type:
Report
System:
The UNT Digital Library
Progress Report for Period Covering January 15, 1960 - February 15, 1960
Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date:
February 15, 1960
Creator:
Petrow, Henry G.
Object Type:
Report
System:
The UNT Digital Library
The Influence of Point Defects on the Mechanical Properties of Lithium Fluoride : First Technical Report
Lithium fluoride crystals were quenched into silicone oil from near the melting point. The return to an equilibrium structure during annealing was observed by means of mechanical tests and etching techniques. Crystals containing three levels of impurity, zone refined, commercially pure, and doped with 0.05 mole per cent magnesium, were used in order to separate the effects of foreign ions from those of thermal vacancies. The changes of mechanical properties produced by quenching and by subsequent annealing were generally attributable to point defect-dislocation interactions. Precision density determinations indicated that about 10% of the equilibrium concentration of vacancies at the melting point was retained at room temperature by the quench. The density could be restored to its normal value by annealing. Two important annealing stages were observed. At about 200 deg C the precipitation of impurities retained in solution by the quench caused a sharp increase in the hardness as measured at room temperature. Isothermal annealing revealed the hardening process to have an activation energy of about 0.5 ev which is probably the energy for migration of an associated magnesium ion-lithium vacancy pair. Between 300 and 400 deg C the removal of dislocations and probably vacancy clusters resulting from the quench …
Date:
January 1960
Creator:
Nadeau, J. & Washburn, J.
Object Type:
Report
System:
The UNT Digital Library
The SNAP II Power Conversion System. Topical Report No. 3. Dynamic Analysis
SNAP II is the designation for a nuclear auxiliary power unit, designed primarily for utilization in the WS117L satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine, and an alternator. Dynamic analysis of the power conversion system was conducted utilizing a comprehensive analog computer simulation. Feasibility of a parasitic load control for numerous system disturbances was demonstrated. This analysis was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 15, 1960
Creator:
Deibel, David L.; Mrava, Gene L. & Seldner, Kurt
Object Type:
Report
System:
The UNT Digital Library
Radioactivation Analysis
The development of nuclear reactors and other nuclear particle sources has given the analyst a new analysis method which can be successfully applied to the determination of microgram and submicrogram quantities of many elements. Known as "radioactivation analysis", this method is one in which an "activation" by some type of nuclear reaction is used to produce a radioactive isotope of the element to be determined. Since this radioisotope decays with its own characteristic radiations and half-life, it is possible to make radioactivation analysis a very specific analysis. Chemical separations of the radioisotope are employed whenever necessary and its radioactivity measured by some type of radiation counter.
Date:
November 30, 1960
Creator:
Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
The Helium Purification System for the Proposed 800 MWT Pebble Bed Reactor
A helium coolant purification system was designed for the proposed 800 MWT Pebble Bed Reactor. The purification system will operate on a coolant side stream with a flow rate 1% of the total coolant flow and there are provisions for radioactive and non-radioactive contamination removal.
Date:
December 7, 1960
Creator:
Scott, C. D. & Suddath, J. C.
Object Type:
Report
System:
The UNT Digital Library
Use of Convergent and Asymptotic Series for Computation of the Modified Bessel Function of the First Kind.
In the Communications of the ACM of April, 1960, p. 240, there appeared two Algol algorithms for the computation of In, the modified Bessel function of the first kind. One of these algorithms uses a convergent series and the other an asymptotic series. Their author, Dorothea S. Clarke, did not give any information with regard to which algorithm is more appropriate in a given situation (a given situation meaning the computation of In (x) for a definite pair of numbers n and x). Such information is necessary, however, if the algorithms are to be useful, particularly since the asymptotic series is in many cases not valid.
Date:
December 12, 1960
Creator:
Bumgarner, L. L.
Object Type:
Report
System:
The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents
The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date:
December 16, 1960
Creator:
Pierce, R. M.
Object Type:
Report
System:
The UNT Digital Library
Steady-State Radial and Axial Temperature Profiles of an E. G. C. R. 5 1/2" O. D. Through Tube During 1500 KW Operation - Part II
The steady-state radial and axial temperature profiles of an E. G. C. R. 5 1/2" O. D. through tube are determined for the test condition of an attemperated fuel assembly operating at 1500 KW in the loop. The profiles are determined for the case of the central control rod fully inserted and bank insertion to 62 inches (Δk = 0.025). The data are presented in the form of tables and curves.
Date:
December 30, 1960
Creator:
Noggle, L. W.
Object Type:
Report
System:
The UNT Digital Library
Thermal-Neutron Flux at the HRE-2 Core Wall, Determined from Zircaloy-2 Induced-Activity Measurements During Runs 13, 14, 16, 17, 18, 19, 20 and 21.
The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-in. from the core center.
Date:
December 20, 1960
Creator:
Baker, J. E.
Object Type:
Report
System:
The UNT Digital Library
Homogeneous Molten Salt Reactors
Multigroup one-dimensional calculations were done recently to obtain estimates of critical masses, power density distributions and fissioning spectra for some homogeneous molten salt reactors having outer reflectors and central "islands," placed inside the currently proposed MSRE vessel. For a 5-inch-thick outer reflector and 1-ft-diamter island, both beryllium, the calculated critical mass is 108 kg; 40 percent of the fissions occur at thermal, and the maximum power density of 3.9 times the core mean power density occurs at the island-salt interface. If the reflector thickness is increased to 10 inches, the critical mass is reduced to 34 kg; 67 percent of the fissions occur at thermal, and the peak power density of twice the core mean again occurs at the core island-salt interface.
Date:
December 13, 1960
Creator:
Nestor, C. W., Jr
Object Type:
Report
System:
The UNT Digital Library
Status Report on the Pneumatic Temperature Measuring system Studies for the EGCR
The pneumatic temperature probe (PIM) is a device for measuring gas temperatures by utilizing the dependency of the flow of gases through a restriction on the temperature and pressure conditions. The determination is made by measuring critical mass flow across a restrictive element such as a nozzle and by knowing the upstream pressure and other variables pertinent to the critical flow equation, computing the temperature at the entrance to the restrictive element. In practice it has been found useful to use two critical flow nozzles in series and measure the ratio of the pressures at the nozzle inlets, together with the temperature at the downstream nozzle. The limitations of present thermocouple materials for long term use at elevated temperatures makes resort to this device attractive on many installations.
Date:
December 30, 1960
Creator:
Hochreiter, H. M.
Object Type:
Report
System:
The UNT Digital Library
After Shutdown Heating in the HFIR
After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.
Date:
December 29, 1960
Creator:
McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Gas Film Resistance in Diffusion from a Porous Septum into a Fluid Stream
The theory of mass transfer into a flowing fluid is utilizes to estimate the effect of gas film resistance on overall rates of transfer through a porous septum. The expressions developed for the mass transfer ratio...
Date:
October 10, 1960
Creator:
Saunders, A. R.
Object Type:
Report
System:
The UNT Digital Library
Removal of Strontium from Wastes
The hazard of Sr^90 arises in part from its fixation by phosphates in the skeletal system. It is natural then to consider compounds and minerals associated with the phosphate anion for applications in waste disposal. Calcium phosphate floc formation is widely used as a method for removing strontium from contaminated water. Also, calcerous soils are said to be effective for removing strontium from low-level wasters containing dissolved phosphates. It is suggested that one the mechanisms involved in strontium removal is the formation of calcium phosphate (apatite), with strontium substituting isomorphously.
Date:
November 28, 1960
Creator:
Tamura, T. & Struxness, E. G.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of EGCR Charge and Service Machines
Methods for the noncorrosive removal of volatile fission products and UO2 dust from carbon steel and stainless steel have been developed. Procedures for applying these methods to the decontamination of the EGCR charge and service machines are described.
Date:
October 13, 1960
Creator:
Meservey, A. B.; Chilton, J. M. & Ferguson, D. E.
Object Type:
Report
System:
The UNT Digital Library
Electrical Design Standards and Graphical Symbols
This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date, and supersedes the previously issued ORNL Electrical Symbols List and CF-58-12-141, Electrical and Electronic Drawing Standards for Wiring and Device Coding and Applications.
Date:
October 1960
Creator:
Bates, A.E.G; Bowelle, M.M.; Horton, J. L.; Moore, R. L.; Hyland, R. F. & Brashear, C.
Object Type:
Report
System:
The UNT Digital Library
High Energy Storage Ceramic Capacitor. Quarterly Report No. 4 [for] August 19, 1957 -- December 31, 1957
The chief purpose of this contract is the development of ceramic materials with high dielectric constant and high dielectric strength values, and suitable for use of dielectrics in capacitors capable of storing large amounts of energy in small volumes. Work performed during the fourth quarter included (1) Material development and sample preparation; (2) Sample testing; (3) discussion of ceramic density measurements; (4) Optical studies of titanates; (5) Fabrication of large ceramics; and (6) Capacitor design.
Date:
October 31, 1960
Creator:
Lupfer, D. A.
Object Type:
Report
System:
The UNT Digital Library
The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing
SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 18, 1960
Creator:
Poulos, Earnest N. & Forman, Edward R.
Object Type:
Report
System:
The UNT Digital Library
Refinements of the Theory of the Infinitely-Long, Self-Acting, Gas-Lubricated Journal Bearing. Interim Report
The lubrication equations for an arbitrary Newtonian fluid are derived directly from the general equations for conservation of mass, momentum, and energy. From the lubrication equations an inequality is obtained for the internal film temperature rise, after which the isothermal film equations are derived. Then, for perfectly-aligned self-acting journal bearings, a conservation equation is obtained. For gas bearings this condition gives: [formula] constant along the axis of the bearing. Application of this condition to the infinitely-long gas bearing gives more accurate pressure solutions for this case. The Katto-Soda form of the differential equation for the infinitely-long bearing is solved by a series expansion in the eccentricity ratio, the first terms of which give the original, approximate Katto-Soda solution. In addition, solutions obtained numerically by digital computations are presented in graphical and tabular form for eccentricity ratios from 0 to 0.9 and compressible bearing parameter [formula]. Design charts based on these calculations are provided.
Date:
January 1960
Creator:
Elrod, Harold G., Jr.
Object Type:
Report
System:
The UNT Digital Library
Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961
During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date:
February 16, 1960
Creator:
Russell, Elizabeth Shull, 1913-2001
Object Type:
Report
System:
The UNT Digital Library
Progress letter No. 11 for January 1, 1960 through January 31, 1960
A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date:
February 15, 1960
Creator:
Baron, Edeard H.
Object Type:
Report
System:
The UNT Digital Library
Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study
The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.
Date:
December 27, 1960
Creator:
King, Blake
Object Type:
Report
System:
The UNT Digital Library