Resource Type
Serial/Series Title
Atomic Energy Commission Reports
206
AEC research and development report
69
University of California Radiation Laboratory Reports
60
UCRL (Series)
53
Report (U.S. Atomic Energy Commission)
52
TID
51
NYO (Series) (New York)
48
Oak Ridge National Laboratory Reports
44
UC (Series)
35
United States Geological Survey Reports
34
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531 Matching Results
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Xenon and Samarium Poisoning
The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date:
January 23, 1961
Creator:
Carlsmith, R. S.
Object Type:
Report
System:
The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications
The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date:
February 14, 1961
Creator:
Moore, S. E.
Object Type:
Report
System:
The UNT Digital Library
Sources and Availability of Helium
A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date:
January 19, 1961
Creator:
Fraas, A. P.
Object Type:
Report
System:
The UNT Digital Library
Some Heat Transfer Characteristics of ORR Fuel Elements
Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date:
January 19, 1961
Creator:
Wett, J. F., Jr.
Object Type:
Report
System:
The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2)
A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date:
January 16, 1961
Creator:
Kasten, P. R. & Cheverton, R. D.
Object Type:
Report
System:
The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3
The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date:
January 13, 1961
Creator:
Butler, T. A. & Pierce, E. E.
Object Type:
Report
System:
The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960
A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date:
January 11, 1961
Creator:
Sadowski, G. S.
Object Type:
Report
System:
The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop
Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date:
January 6, 1961
Creator:
Griess, J. C.; Baker, J. M. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis
Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is increased to the point where the level scram must be set above 50 Mw).
Date:
January 4, 1961
Creator:
Stone, R. S. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.
The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release. Two of the most important variables not investigated in the present report are the influence of metal cladding and the difference in internal nuclear heating as opposed to external radiant heating. In addition a significant uncertainty exists in the understanding of diffusion through large masses such as might result from a scaled-up melt down in a reactor.
Date:
February 8, 1961
Creator:
Parker, G. W.; Creek, G. E. & Martin, W. J.
Object Type:
Report
System:
The UNT Digital Library
Design Study of a Pebble-Bed Reactor Power Plant
Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.
Date:
May 11, 1961
Creator:
Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Section C Progress Report for October-November 1960
Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain rapid and efficient dissolution of the soluble thorium fraction. The cost of treating granite was estimated at $3.50-5.20 per ton, variations within this range being dependent primarily on differences in acid consumption for different granites. Estimated costs per pound of thorium plus uranium recovered ranged $30-500.
Date:
March 3, 1961
Creator:
Brown, K. B.
Object Type:
Report
System:
The UNT Digital Library
Radioactivation Analysis
The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radiation and half-life, it is possible, through radiochemical measurements following radioactivation, to devise a method of analysis which is very specific for particular elements. Whenever necessary, the radioisotope is separated by chemical means and its radioactivity is then measured by some type of radiation counter.
Date:
September 22, 1961
Creator:
Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment
The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date:
May 8, 1961
Creator:
Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
Object Type:
Report
System:
The UNT Digital Library
Electrical and Electronic Symbols & Drawing Committee
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. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain elements, such as the transistor, have come into common use. Committee and represent the symbols have been selected after considerable study by the Committee and represent the symbols that seem to be standard Reference Information series, Interim E--1.
Date:
November 1961
Creator:
Bates, A.E.G
Object Type:
Report
System:
The UNT Digital Library
Plutonium Release Incident at Oak Ridge National Laboratory
A nonnuclear explosion involving an evaporator occurred in a shielded cell in the Radiochemical Processing Pilot plant at Oak Ridge National Laboratory. Plutonium released from the processing cell contaminated areas in the pilot plant building and nearby streets and building surfaces. The explosion is considered the result of rapid reaction of nitrated organic compounds formed by the inadvertent nitration of about 14 liters of a proprietary decontaminating reagent.
Date:
January 10, 1961
Creator:
King, L. J. & Bresee. J. C.
Object Type:
Report
System:
The UNT Digital Library
Unit Operations Section Monthly Progress Report September 1960
Measurements of the interfacial tension between water and tributyl phosphate solutions were made for application to the analysis of Marengoni effect in solvent extraction. A 24 hr flame calcination run to product Th02 particles yielded 40% as product and 54% collected from the furnace walls and from a coarse particle trap. The elution rates of uranyl ion from Dowex 21K using sodium nitrate could be approximated by assuming apparent diffusion coefficients of 1.67 x 10^-7 and 1.18 x 10 ^-7 cm^2/sec, respectively for 960µ and 820µ resn while the corresponding apparent coefficients using sodium chloride were 1. 78 x 10^-7 and 1.27 x 1-^-7 cm^2/sec. The reacting surface of ThO2 Universal Match Co. pellets was determined as a function of fraction dissolved. The lead scews and companion nuts from both the multipurpose saw and dejacketing machine were coated with a baked on lubricant. In Zirflex decladding studies using 4.5 M NH4F - 0.5 M NH4NO3, the average dissolution rate of Zircaloy-2 was decreased only 10% when the overhead condensate was withdrawn and 1.0 M NH4OH was added to maintain the volume.
Date:
January 27, 1961
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
High Power Density Development Project Sixth Quarterly Progress Report: July-September 1961
During the quarter the development program was continued as scheduled. Milestones that were reached included the successful irradiation of prototype Big Rock fuel bundles in VBWR to a level above 2500 MWD/T with power densities as high as 88 kw/1. Also completed was the scheduling computer specification followed by a formal solicitation of bids through the AEC. A summary of progress by task is presented here.
Date:
1961
Creator:
Holland, L. K.
Object Type:
Report
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: July 1, 1961-September 30, 1961
This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the first quarter of fiscal year 1962. The data are summarized in Section II.
Date:
December 21, 1961
Creator:
Danielson, D. W. & Gilbert, R. S.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Program - A Boilng Water Reactor Research and Development Program. Fifth Quarterly Report, July 1961-September 1961
This report summarizes progress on investigation into improving the technological limits of boiling water reactors, Vallecitos Boiling Water Reactor and other facilities.
Date:
October 10, 1961
Creator:
Hodde, J. A.
Object Type:
Report
System:
The UNT Digital Library
Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model
Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.
Date:
September 1961
Creator:
Swan, C. L.
Object Type:
Report
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961
This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
Date:
August 25, 1961
Creator:
Danielson, D. W.
Object Type:
Report
System:
The UNT Digital Library
Control Worth of B4C Rods
This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.
Date:
August 30, 1961
Creator:
Pomraning, G. C. (Gerald C.)
Object Type:
Report
System:
The UNT Digital Library
Plan For VBWR Stability Experiment
Stability tests are to be made in the VBWR (boiling water reactor). The tests are of three types: steady state measurements, rod oscillator tests, and transient tests.
Date:
August 30, 1961
Creator:
Cook, W. H.; Hodde, J. A.; Howard, C. L. & Niemi, R. O.
Object Type:
Report
System:
The UNT Digital Library