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Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element

Description: It is assumed that when a hole appears in the cladding of a reactor fuel tube the fission products in the space between the fuel and the cladding will diffuse towards the hole. There they are swept away by the flow of steam past the hole. The process of diffusion is assumed to be governed by the ordinary diffusion equation with the boundary condition that the density of the fission products is zero at the surface of the hole. The diffusion equation is solved for the case of steady-state emissio… more
Date: July 26, 1956
Creator: Helstrom, Carl W.
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The Grüneisen Parameter for an Einstein Solid and Under Finite Strain

Description: The Grüneisen constant, as evaluated from the equation of state, is obtained for an Einstein solid. the presence of a state of finite hydrostatic pressure is taken into account explicitly by means of Murnaghan's theory of finite strain, to obtain the Grüneisen parameter's on the Debye and Einstein models. Results are identical in the two cases with the corresponding values obtained without use of the formal theory of finite strain.
Date: September 26, 1955
Creator: Gilvarry, J. J. (John James), 1917-
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Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab

Description: A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy dis… more
Date: October 26, 1960
Creator: Aulender, S. & Trubey, D. K.
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Additional Miscellaneous Tools in the HRT Core

Description: This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.
Date: September 26, 1960
Creator: Holz, P. P.
open access

Sizes of U. S. Steam- Electric Plants

Description: At the present time, plants in the 100-500Mv size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the U.S. utilities industry. The contribution of plants of over 1,000-Mv capacity is increasing more rapidly than any other size clarification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mv. The largest steam-electric plant in the U.S. is the TVA plant at Kin… more
Date: May 26, 1959
Creator: Robertson, R. C.
open access

The Development of a Fluidized Bed Reactor for the Fluorox Process: Unit operations Monthly Status Reports for the Period November, 1958, Through May, 1959

Description: Results of four experiemental runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF6 production from UF4 by use of dry air of O2, 2UF4 + O2 = UF6 + UO2F2, in an Inconel fluidized bed reactor at 800-850°C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF6 was collected or measured. Two runs made with crude UF4 (produced from unpurified mill concentrate) as the feed material, showed that UF6 could be pro… more
Date: May 26, 1959
Creator: Bresee, J. C.; Scott, C. D. & Horton, R. W.
open access

Determination of Trivalent Uranium in Fluoride Salt Mixtures by the Modified Hydrogen Evolution Method

Description: The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium… more
Date: February 26, 1956
Creator: White, J. C.; Meyer, A. S., Jr.; Vaughan, W. F.; Ross, W. J. & Manning, D. L.
open access

Interim Evaluation of the Fluorox Process for UF4 and UF6 Manufacture

Description: The conversion of UNH to UF4 and UF6, utilizing moving-bed techniques, is being studied; sufficient progress has been made that an evaluation of the process is warranted. The procedures under study, the Fluorox Process, have three major advantages: (1) substitution of HF for high-cost fluorine, (2) considerable reduction in HF requirements, and (3) marked reduction in plant-size and mechanical complexity.
Date: May 26, 1955
Creator: Moore, J. E.
open access

The Combination of Hydrogen and Oxygen in Platinum Catalyzed Flow Reactions

Description: An extension of the concepts advanced by Langmuir regarding the nature of the platinum catalyzed oxidation of hydrogen and the application of the resulting theory to the experimental data observed by Ranschoff and Spiewak for an HRE type recombiner indicates that their data are corrected by the dimensionless equation (see report) equally well, with a mean deviation of 3.8 percent. This expression is recommended as a basis for the design of catalytic recombiners. The catalytic combinations is pi… more
Date: October 26, 1954
Creator: Garber, Harold J. & Peebles, Fred N.
open access

Magnetic Measurement of AGS Experimental Magnets

Description: This is a preliminary report on the magnetic measurements taken to date on the AGS experimental magnets. It mainly summarizes the results which were necessary for the setting up of the proton separated beam in August 1961. A few curves on information obtained since then are included. When the study is finished, a complete report on all phases of the work, including the methods used, will be forthcoming.
Date: December 26, 1961
Creator: Danby, Gordon T.
open access

The Fast Rise Pulser

Description: A circuit is described developed to fill the need for a pulser with a 15-20 volt amplitude into the 93 ohm line, stable, transistorized and low cost, fast 10 Nano second rise, and a variable repetition period from 0.5 sec. to 4 sec.
Date: June 26, 1962
Creator: Kiriokos, George
open access

Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels Design Criteria for Metal Solution Storage

Description: Facilities shall be provided in the 221-U Building for storing the metal solution product of the dissolution step in existing tankage from U, T, and B Plants until a reprocessing campaign is scheduled through Redox. This section shall provide a sampling tank for fuel accountability sampling and a pump tank from which the solution will be pumped via a cross-country pipeline to Redox for further processing.
Date: April 26, 1960
Creator: Duda, R. F.; Graf, W. A. & Kligfield, G.
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The Experimental Application of Neutron Capture Therapy to Glioblastoma Multiforme

Description: The rapid development of the field of atomic energy during the past few years now permits the exploration of applications to medicine involving new concepts in the treatment of cancer. One such has been the study of neutron capture therapy which is being developed at the Brookhaven National Laboratory.
Date: July 26, 1954
Creator: Farr, Lee, E., M. D.
open access

Pilot Plant Fluorination of Uranium Fuel Elements by Bromine Trifluoride

Description: The so-called Fluoride Volatility Processes refer to several proposed non-aqueous methods of processing irradiated fuel elements. In each of these methods, the uranium is fluorinated to uranium hexafluoride and then decontaminated by distillation. One of the methods, involving direct fluorination of the uranium by bromine trifluoride, has been under investigation at BNL since 1950; subsequently a pilot plant was built to study this step of the process. The objectives of the program were to inve… more
Date: July 26, 1956
Creator: Strickland, G.; Horn, F. L. & Johnson, R.
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Trough-Time Dissolver

Description: Designing a dissolver safe for up to 5 per cent U.235 enriched NPF's and having a one a ton per day capacity is a fundamental problem of Hanford NPF Program. Two basic design concepts have so far evolved, both of which employ a recirculating system in which the fuel elements are placed in the critically safe geometry separated from the bulk of the solution in another vessel. In one concept the fuel elements are charged to a set of geometrically safe cylinders or tubes and solution is circulated… more
Date: June 26, 1959
Creator: McKee, R.W.
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Scratch Depth Measurement Methods

Description: Judging scratch depth or surface roughness by unaided visual inspection under controlled conditions, while rapid and popular, is not quantitative. Comparison methods improve reproducibility but are generally not applicable to evaluation of depths of single widely spaced scratches. Stylus-type contour recorders yield valuable scratch contour data but may themselves plow through soft materials and fine details. Depth measuring microscopes are particularly applicable to measurement of pinhole dept… more
Date: February 26, 1959
Creator: Brenden, B.B.
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Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
open access

A Note Concerning the "100% Value" in Iron Absorption Studies by Whole Body Counting

Description: The evaluation of iron absorption using a single crystal whole-body counter is complicated by the inherent difficulty of determining a correct "100% value". Shortly after ingestion, tracer radioiron can be found in the stomach, upper small intestine, portal circulation and liver. Fourteen to twenty days later, the time at which absorption is measured most effectively, the radioiron will be distributed between the red cell mass, liver, spleen, bone marrow and other storage areas. With this mixed… more
Date: March 26, 1963
Creator: Schiffer, L.; Price, D. C.; Cuttner, J.; Cohn, S. H. & Cronkite, E. P.
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