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Perturbation-Theory Rules for Computing the Self-Energy Operator in Quantum Statistical Mechanics

Description: Highly convenient rules are given for the general term in the time- independent perturbation-theory expansion for the self-energy operator of quantum statistical mechanics. The rules are derived by starting from the usual formalism involving time-independent Green's functions. The well-known formulas for thermodynamic quantities in terms of the self-energy operator are included for completeness. (auth)
Date: December 17, 1962
Creator: Baym, G. & Sessler, A. M.
Partner: UNT Libraries Government Documents Department
open access

Production test IP-555-A sodium silicate as a corrosion inhibitor

Description: The objective of this test is to operate one of the 1706-KE single pass tubes using sodium silicate rather than sodium dichromate as the corrosion inhibitor and to monitor the radioisotope concentration in the effluent. Single pass tube tests carried out under Production Test IP-484-A have demonstrated that when sodium silicate is added to process water the concentrations of significant radioisotopes in the effluent are reduced by a factor of two. At the concentrations investigated., the use of… more
Date: December 17, 1962
Creator: Geier, R. G. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION

Description: An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight ba… more
Date: October 17, 1962
Creator: Prince, C. E. & Milford, R. P.
Partner: UNT Libraries Government Documents Department
open access

Planning for Uranium Carbide Transient Heating Experiments in Treat

Description: The initial experimental program to study the transient heating of uranium carbide fuel in TREAT is outlined. Preliminary analyses are presented for the behavior of an HNPF prototype UC fuel slug during power bursts in the TREAT reactor. The analysis and evaluation conducted, center around the proposed utilization of the existing GE capsule, and indicate that this equipment will be suitable for the initial uranium carbide experiments with minor modification. A survey is presented and found not … more
Date: October 17, 1962
Creator: Silberberg, M. & Spiegler, P.
Partner: UNT Libraries Government Documents Department
open access

SNAP-50 space powerplant

Description: No Description Available.
Date: September 17, 1962
Partner: UNT Libraries Government Documents Department
open access

USE OF THE DRY MAINTENANCE FACILITY FOR HRT MAINTENANCE

Description: A portable shield was utilized in performing nine semidirect dry maintenance jobs on the HRT. The shield proved to be completely reliable, affording a considerable savings in maintenance costs and reactor downtime. (auth)
Date: September 17, 1962
Creator: Jarvis, J.P.
Partner: UNT Libraries Government Documents Department
open access

THE DETECTION OF BOILING IN A WATER-COOLED NUCLEAR REACTOR

Description: Measurements made at ORNL to study the feasibility of boiling detection in a water-cooled nuclear reactor are described. The methods selected for the detection of boiling include measurement of the acoustical noise produced by the generation of bubbles and measurement of changes in the reactor-power spectral density produced by bubbles. Preliminary results indicating that both methods could detect boiling are shown. (auth)
Date: August 17, 1962
Creator: Colomb, A.L. & Binford, F.T.
Partner: UNT Libraries Government Documents Department
open access

Experiment Facilities of the Oak Ridge Graphite Reactor

Description: Up-to-date descriptive material and dimensional sketches of the ORNL Graphite Reactor and its experimental facilities are presented. (P.C.H.)
Date: August 17, 1962
Creator: Sheppard, S. D.
Partner: UNT Libraries Government Documents Department
open access

The Thermal Expansion of Five Titanium Carbide Cermets from 68 to 1800F

Description: This technical report presents measurements of the thermal expansion of five titanium carbide type cermets from 68 to 1800F. These cermets are designated by Kennametal, Inc., as K 138A, K 150A, K 152B and K 162B. They contain from 64 to 80 weight percent titanium carbide, 10 to 30 weight percent metal binder and 6 to 10 weight percent other carbides. The metal binders are cobalt, nickel, and nickel and molybdenum. An attempt was made to calculate the thermal expansion of each type cermet fr… more
Date: August 17, 1962
Creator: Harrington, L. C. & Rowe, G. H.
Partner: UNT Libraries Government Documents Department
open access

Correlation of Critical Mass Data on Light Water Moderated, Fully Enriched Uranium, Stainless Steel Reactors. Part 1

Description: Experimental data were collected on over 70 light water moderated, fully enriched uranium, stainless steel, critical cores. An equation for the critical mass of cores with a buckling of 0.007 cm/sup -2/ that is lineally dependent on stainless steel volume fraction and grams of B/sup 10/ was compared with available critical experiments and found to yield reasonable results. A correlation method, relating buckling to ( xi SIGMA /sub s// SIGMA /sub a/) was found to fit the available experiments. (… more
Date: July 17, 1962
Creator: Lee, D. H.
Partner: UNT Libraries Government Documents Department
open access

CONCEPTUAL DESIGN OF THE PEBBLE BED REACTOR EXPERIMENT

Description: The Pebble-Bed Reactor Experiment (PBRE) was designed to advance the pebble-bed concept by providing a test of characteristic features and make contriliutions to the general development of all-ceramic gas-cooled reactors. The following objectives were established for the reactor experiment: to investigate key features of the pebble-bed concept, including on-stream fuel handling, movement of fuel through bed, and performance of core; to obtain operation and maintenance experience with a system c… more
Date: May 17, 1962
Partner: UNT Libraries Government Documents Department
open access

DETERMINATION OF THE TRUE STRESS-STRAIN PROPERTIES OF BRITTLE MATERIALS TO 5000 F. Ninth Monthly Report

Description: The development of the system and techniques to permit determination of strains at right angle to the axis of loading in the specimen was continued. An additional optical system was developed to accept the lateral image of the gage points and project a vertical image of the same proportion to the apertures of the strain analyzer. Using a dummy specimen of steel in the load train, the automatic pressure control system for the gas-bearing universals was operated. A fluctuation of gas pressure occ… more
Date: May 17, 1962
Creator: Digesu, F.J. & Pears, C.D.
Partner: UNT Libraries Government Documents Department
open access

Collapse of tubes by external pressure

Description: The problem of tube collapse by external pressure has been investigated experimentally. A graphical solution developed to simplify inelastic collapse design problems was shown to agree with the test results. The von Karman reduced modulus was used in the graphical solution to correct for the stress redistribution caused by yielding. The effects of the geometric imperfections of ovality and wall thickness variations on collapse pressure were shown to be related to the stress-strain behavior of t… more
Date: April 17, 1962
Creator: Kennedy, C. R. & Venard, J. T.
Partner: UNT Libraries Government Documents Department
open access

FUNDAMENTAL STUDIES OF RADIATION DAMAGE IN GRAPHITE

Description: Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energy of the lattice because of interstitial and vacancy defects. Radiation changes such as stored energy and dimensional expansions can be removed by thermal annealing in which the graphite is removed from the radiation field and heated to a temperature above the irradiation temperature. The thermal annealing of irradiated graphites shows that the greater the irradiation dose, the greater is the rec… more
Date: April 17, 1962
Creator: Schweitzer, D.G.
Partner: UNT Libraries Government Documents Department
open access

Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates

Description: Two methods were used for predicting the maximum permissible burnup in type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on UO/sub 2/ stainless steel dispersion fuel plates. Results with two analytical models indicated that burnups above 100% U/35 are permissible. Comparison of the expected burnup with available irradiation data indicates that successful performance of type 3 replacement cores in SM-1, SM-1A, and PM-2A can be expected. (auth)
Date: March 17, 1962
Creator: Wilder, A. S. & Lelleman, R. W.
Partner: UNT Libraries Government Documents Department
open access

CONTROLLED-POTENTIAL COULOMETRIC TITRATION OF URANIUM(VI) IN THE PRESENCE OF NITRATE

Description: A study into the use of sulfamic acld as a nitritedestroying reagent in the controlled-potentlal coulometrlc tltratlon method for uranlum(VI) was made. When nltrites are thus destroyed, the tltration ls much less subject to error from HNO/sub 3/. The results of titratlons of known amounts of uranlum(VI) in the presence of varlous amounts of HNO/sub 3/, Th(NO/sub 3/)/sub 4/, Al(NO/sub 3/ )/sub 4/, and LiNO/sub 3/ are given. (auth)
Date: January 17, 1962
Creator: Shults, W.D.
Partner: UNT Libraries Government Documents Department
open access

Development and evaluation of spire pulse for AlSi lead-dip canning

Description: In the AlSi process, the I&E fuel element is assembled in a two-piece aluminum container consisting of an outer cylindrical shell and an inner tube containing an integrally impacted cap wafer which forms the top end and cap during canning. Both autoclave failures and reactor failures have been attributed to porosity in the AlSi and non-wetting of the aluminum wafer with AlSi. Porosity and non-wetting in the area of the cap closure provides a pathway for water to penetrate through to the uranium… more
Date: January 17, 1962
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
open access

Digital-to-Analogue Converter (Punched Tape to X-Y Plotter)

Description: A digital-to-analog converter is described which is a part of a system that converts punched-tape digital data to analog data in a series of points drawn by an x-y plotter. The converter is designed to plot accurately tapes that contain information other than coded numerical coordinates. Operation of the converter is also described along with format requirements and power supplies. (J.R.D.)
Date: January 17, 1962
Creator: Wall, G. N.
Partner: UNT Libraries Government Documents Department
open access

Digital-to-Analogue Converter (Punched Tape to X-Y Plotter)

Description: A digital-to-analog converter is described which is a part of a system that converts punched-tape digital data to analog data in a series of points drawn by an x-y plotter. The converter is designed to plot accurately tapes that contain information other than coded numerical coordinates. Operation of the converter is also described along with format requirements and power supplies. (J.R.D.)
Date: January 17, 1962
Creator: Wall, G. N.
Partner: UNT Libraries Government Documents Department
open access

Optimum Flow Distribution for Multicomponent Isotope Separation in a Single Cascade

Description: The separation of isotopic mixtures containing three components in a gaseous diffusion cascade operating over an infinite reservoir is discussed. The flow distribution yielding the smallest total flow per unit product was found and compared with the flow distributions in some other theoretical cascades. Curves are presented to show the number of stages required, the total flow and the concentration gradients for both light and middle isotope separation. (auth)
Date: January 17, 1962
Creator: Murphy, J. E.
Partner: UNT Libraries Government Documents Department
open access

Rear face piping study at elevated bulk outlet temperature: KE Reactor

Description: The work described in this report was authorized under Development Test IP-419-E. The primary objective of this study was to establish the stress, hydraulic and vibration conditions which exist in KE Reactor rear face piping components under maximum presently authorized operating conditions and evaluate these conditions from the standpoint of continuity of reactor operation. Test data were recorded at various levels of operation up to and including the maximum authorized bulk outlet temperature… more
Date: January 17, 1962
Creator: Frieling, D. H. & Hutton, P. H.
Partner: UNT Libraries Government Documents Department
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