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NACA Research Memorandums
211
Atomic Energy Commission Reports
90
Hanford Works Reports
48
HW (Series)
37
NACA Technical Reports
25
Oak Ridge National Laboratory Reports
20
University of California Radiation Laboratory Reports
19
TID
13
National Bureau of Standards Reports
11
ORNL (Series)
10
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Radiation Damage to Vacuum Chamber Walls
"The problem of radiation derange to the walls of two types of vacuum chamber for the 6 Bev Cambridge Electron Accelerator was studied. Radiation damage may arise from the synchrotron radiation and from electrons which are not accepted at injection. The synchrotron radiation produces a large amount of secondary x radiation which is isotropic, and therefore complicates the arrangement of internal shielding. The 20 Mev electrons from the lines cannot be attenuated by shielding. It is concluded that dosages of the order of 10/sup 7/ rad/day near the inflector are unavoidable. This would exceed the allowable dosage for a tube made by cementing a stainless steel liner to supporting ribs, and also exceed the test dosages (so far as we know) for alumina ceramics."
Date:
September 10, 1957
Creator:
Stearns, Brenton
Object Type:
Report
System:
The UNT Digital Library
Periodic Radiation Survey. Section II. 4182-EFPH. Second Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)
The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions were the Auxiliary Chamber and the limited access areas between the containers. The highest radiation level obtained in the survey was >2500 MR/HR at the reactor chamber walkway.
Date:
November 10, 1959
Creator:
Ritz, William C.
Object Type:
Report
System:
The UNT Digital Library
Radial Vibrations in Short, Hollow Cylinders of Barium Titanate
The mathematics has been developed for the determination of the radial coupling coefficient for a hollow cylinder of electro-strictive material whose length is small compared to its outside diameter.
Date:
December 10, 1954
Creator:
Stephenson , C. V.
Object Type:
Report
System:
The UNT Digital Library
A Human Engineering Guide to the Arrangement of Elements on a Control Panel
This memorandum is a compilation of general information concerned with the arrangement of elements on a control panel. Arrangement considerations that lead to to improved ease and accuracy of operation are presented to assist the engineer in designing new control panels.
Date:
December 10, 1954
Creator:
Williams, H. L.
Object Type:
Report
System:
The UNT Digital Library
Frequency Components of a Step Function and a Sinusoid
Fourier analyses are made on two functions. The first is a step function forward from periodic samples of a sinusoid. If the frequency of the sinusoid is less than one-half of the sampling frequency, it is shown that the step function has no frequency components less than one-half of the sampling frequency other than that of phase, and duration with respect to the interval of the analysis. It is shown that the insertion of a blank space in the period of analysis reduces greatly the uncertainty of the amplitude of the initial sinusoid as estimated from the results of the Fourier analysis. The results of the analyses are useful in the design and evaluation of certain analog data-analyzing systems.
Date:
May 10, 1955
Creator:
McGehee, R. M.
Object Type:
Report
System:
The UNT Digital Library
Plasma Accumulation in a Device Fed by Energetic Ion Trapping
Simon (1960) has given a general steady state theory of plasma accumulation (without energy losses) in an OGRA device. Such a device is fed by injection of energetic molecular ions which dissociate to produce trapped protons. Initial trapping is achieved by dissociation in the background gas. Such a device is usually characterized by a critical input current of critical plasma density (a function of input current) above which plasma density builds up to a value limited by Coulomb-scattering losses. For a regime of operation of current interest at Oak Ridge National Laboratory (600-kev hydrogen molecular ion injection and dissociation, highly efficient ion-pumping action of the trapped plasma), extremely simple approximate formulas have been derived which describe with a fair degree of accuracy the critical current of density for plasma build-up.
Date:
November 10, 1960
Creator:
Mackin, R. J., Jr.
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
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
Determination of Li6 in Aqueous Solution by Neutron Activation Analysis
A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date:
July 10, 1959
Creator:
Winchester, J. W. & Bate, L. C.
Object Type:
Report
System:
The UNT Digital Library
Solids Accumulation and Fission Heating in the HRT Chemical Plant Underflow Pot (Co-op Report, Fall Quarter, 1958)
The purpose of this study was to develop equations for calculating fision product heating in the HRT-CP underflow pot from measured temperatures and to attempt to correlate the rat of solids accumulation in the underflow pot with fission heating and reactor power. Using fission heating data calculated from relating solids accumulation and heating have been tested. In one case an error of no greater than 26% was incurred in the calculation of the total weight of solids collected during chemical plant runs 17-4, 17-5, and 17-6. Further development work will be done on this correlation.
Date:
June 10, 1959
Creator:
Dunn, W. E.
Object Type:
Report
System:
The UNT Digital Library
Thorium oxide Slurry Falling Ball Viscometer : Final Co-op Report, Winter, 1957
A falling ball viscometer under development at ORNL, employing a flow system and an electromagnetically operated dash-pot pump, was evaluated for possible use with aqueous ThO2 slurry systems under reactor irradiation. Interchangeable check valve inserts were designed and fabricated to investigate several pump designs. Magnetic flux concentrations which originally prevented circulation of the ferritic stainless steel viscometer ball through the electromagnetic pump were eliminated by substitution of iron-magnetic stainless steel inserts. Viscosity was correlated through a logarithmic plot of the dimensionless Reynolds number vs. Froude number with the ratio of ball diameter to tube diameter as a parameter. The relation is linear in the laminar flow region.
Date:
April 10, 1957
Creator:
Novak, P. E.
Object Type:
Report
System:
The UNT Digital Library
Delay Time Prior to Dumping the HRT
Some refined calculations have been made, relative to a proposed delay prior to a dump, to determine the expected D2 concentration in the vent stream from the pressurizer gas bleeds during a dump of the Homogeneous Reactor Test (HRT). These calculations indicate that for vent valves have a Cv of 0.07 (venting time from 2000 psia to D2O saturation pressure of approximately 12 minutes), a delay period is not required since the D2 concentration is well below lower explosive limit. For vent valves having a Cv of 0.3 (venting time approximately 2.4 minutes), the calculation indicate that a delay before venting of approximately two minutes will be required. This is due entirely to the possibility of mass ebullition the D2. Since the pressure drops so quickly, the reactor solution becomes saturated with D2 before appreciable recombination can occur.
Date:
January 10, 1957
Creator:
Gift, E. H. & McLain, Howard A.
Object Type:
Report
System:
The UNT Digital Library
The Pressure Bridge Density Meter for Continuously Metering Densities of Flowing Streams
A new type of continuous density meter, applicable for use with ThO2 slurry in high temperature-pressure systems, was tested successfully in a low temperature slurry loop.
Date:
January 10, 1957
Creator:
Wichner, R. P. & VandenBulck, C. F.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Program, A Boiling Water Reactor Research and Development Program Eighth Quarterly Progress Report April 1962 - June 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors in several areas. This report presents updates on tasks related to those areas.
Date:
July 10, 1962
Creator:
Hodde, J. A.
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
VARI-II
Writing the VARI-II Program was motivated by the need for a method of analyzing the results for the Absorber Burn-Up Experiment in progress at the Vallecitos Atomic Laboratory.
Date:
March 10, 1961
Creator:
Russell, J. L. (John L.), Jr.
Object Type:
Report
System:
The UNT Digital Library
Leaching and Precipitation Tests on Grants Ores
Leaching tests were run on two samples from the Grants area in New Mexico. Uranium extractions of 94 per cent were obtained by leaching Sample 6-1 with solutions containing 240 lbs. of Na2CO3 and 60 lbs. of NaHCO3 per ton and by leaching Sample 6-2 with 270 lbs. of Na2CO3 and 180 lbs. of NaHCO3 per ton. Cyclic tests were completed using caustic precipitation of the leach liquor.
Date:
September 10, 1951
Creator:
Abrams, Charles S. & George, D'Arcy R.
Object Type:
Report
System:
The UNT Digital Library
Operation of the ORNL Graphite Reactor and the Low-Intensity Test Reactor — 1955 LITR Flux Traverses
The ORNL Graphite Reactor operated very well during 1955. The downtime was low, only 8.6%. The fuel in the bonded slugs did not perform as well in 1955 as in 1954. Much of the trouble was undoubtedly due to growth of slugs which were not beta-transformed. It is known that some slugs had grown over 1/2 in. The automatic central system installed in 1954 continued to operate satisfactorily. The cooling system gave minor trouble when one of the 900-hp fan meters had to be replaced because of shorts in the rotor. The high radiation in the canal was the largest source of trouble. Approximately 55 tons of slugs discharged from the reactor in 1952 was sent to the Metal Recovery Plant. Enough slugs had raptured, due to their long exposure in the canal and reactor, to badly contaminate of water. Most of the contamination was removed by the end of the year, but the radioactivity which had soaked into the canal wells was enough to give high radiation fields. A solution to this problem was being sought at the end of the year. A study is under way on the possibility of increasing the flux of the ORNL Graphite Reactor …
Date:
September 10, 1956
Creator:
Rupp, A. F. & Cox, J. A.
Object Type:
Report
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report for Period Ending July 31, 1955
Construction of the HRT reactor shield tank was completed, and the inside surfaces were painted. The roof structure for the tank is being assembled in preparation for an acceptance pressure test. Service piping and instrument lines are being installed in the central room area by ORNL craft forces. This work is approximately 50% complete. Fabrication of all temperature system components, except the blanket outer storage tanks, has been completed.
Date:
October 10, 1955
Creator:
McDuffie, H. F. & Kelly, D. C.
Object Type:
Report
System:
The UNT Digital Library
A Fused Salt—Fluoride Volatility Process for Recovery and Decontamination of Uranium
A preliminary chemical flowsheet is presented of a fluoride volatility process for recovering and decontaminating uranium from heterogeneous reactor fuels after dissolution in a fused salt. In laboratory work, a gross β decontamination factor of > 10 4 was obtained in the fluorination of a UF4-NaF-ZrF4 melt by passing the product UF6 through NaF at 650°C. The solubility of UF6 in molten NaF-ZrF4 was shown in kinetic studies to cause a lag in the evolution of UF6 from the fluorinator. Corrosion of nickel in the fluorination step appeared to be 2-4 mils/hr during the time that uranium was present. The average corrosion rate over the process as a whole was less than O.4 mil/hr. Earlier studies were reported in ORNL-1709 and 1877.
Date:
October 10, 1955
Creator:
Cathers, G. I. & Bennett, M. R.
Object Type:
Report
System:
The UNT Digital Library
Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960
A 19-rod Zircaloy-clad half-length PRTR spike element successfully irradiated to high plutonium burnout at full power in the ETR shoved partial bonding of the core and cladding. Unsatisfactory autoclave films on the Zircaloy cladding of the PRTR Al-Pu fuel elements are delaying final assembly of the first 30 clusters. Further conditioning of the autoclaves and the availability of permanent etching facilities are expected to correct the present difficulties.
Date:
May 10, 1960
Creator:
Hanford Laboratories Operation Irradiation Procesing Department
Object Type:
Report
System:
The UNT Digital Library
EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment
The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date:
May 10, 1960
Creator:
Nichols, P. F.
Object Type:
Report
System:
The UNT Digital Library
The Preparation of Plutonium Powder by a Hydriding Process--Initial Studies
Powder metallurgy is rapidly gaining importance as a means of fabricating nuclear fuel elements and other reactor components. It provides a convenient method for forming metals, unusual combinations of metals, and metal-ceramic combinations. The unique features of this technique which make it desirable for nuclear engineering purposes are the following:
Date:
March 10, 1960
Creator:
Stiffler, G. L. & Curtis, M. H.
Object Type:
Report
System:
The UNT Digital Library
Gas-Graphite Reactions. I. Thermal and Microwave Oxidation of Various Reactor-Grade Graphites*
Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.
Date:
February 10, 1960
Creator:
Clark, T. J.
Object Type:
Report
System:
The UNT Digital Library