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Seal-Shell-a Digital Program to Determine Stresses and Deflections in an Axisymmetric Shell of Revolution

Description: SEAL-SRELL, a FORTRAN II program registered as code number M0077 at Bettis Atomic Power Laboratory, is written for the Philco 2000 computer with two tape units. The program is designed to determine loads, deflections, and stresses in a thin shell of revolution under axisymmetric end loads and pressure. (auth)
Date: September 1, 1961
Creator: Friedrich, C.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMPILER INTO GEORGE ASSEMBLY ROUTINE

Description: This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source la… more
Date: June 1, 1962
Creator: George, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER

Description: EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, g… more
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multigroup Calculations of Effective Delayed-Neutron Fractions, Prompt- Neutron Lifetime, and Related Kinetics Parameters. IBM-704 Program 1188/RE

Description: In the course of a recent study of kinetics parameters, it was found that RE-185, because of its limitations, was inadequate to handle the problems involved with the reactors considered. Program ll88/RE was written entirely independent of and is intended to make RE-185 obsolete. The multigroup calculations of primary interest performed by the code are as follows: the total effective delayed-neutron fraction and its distribution into six ' families'' which are characterized by their periods; the… more
Date: March 1962
Creator: Kvitek, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A FORTRAN Program for Calculating Single Crystal Absorption Corrections

Description: A Fortran program is described for calculating the absorption correction for application to single crystal x ray or neutron intensity measurements. The program is available in the form of symbolic punched cards. InstrucPions are included. (J.R.D.)
Date: April 1, 1962
Creator: Wehe, D. J.; Busing, W. R. & Levy, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NIGHTMARE-AN IBM 7090 CODE FOR THE CALCULATION OF GAMMA HEATING IN CYLINDRICAL GEOMETRY

Description: The NIGHTMARE program calculates the gamma-dose rate at any point in or near a reactor by means of the NDA buildup-factor method. The source distributton is obtained from a two-group, two-dimensional diffusion code (EQUIPOISE-2). Seven gamma-energy groups are used. As many as nine different concentric cylindrical regions may be considered, but only radial variation of attenuation and buildup properties is permdtted. Two schemes of estimating buildup factors through a succession of materials are… more
Date: February 26, 1962
Creator: Tobias, M.L.; Vondy, D.R. & Lietzke, M.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A System for Generating Gamma Ray Cross Section Data for Use with the IBM-7090 Computer

Description: A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)
Date: May 16, 1962
Creator: Penny, S. K.; Emmett, M. B. & Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TWO AUXILIARY CODES FOR USE WITH RENUPAK

Description: Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date: August 10, 1962
Creator: Trubey, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SPECIFIC HEAT DATA ANALYSIS PROGRAM FOR THE IBM 704 DIGITAL COMPUTER

Description: A computer program was developed to calculate the specific heat of a substance in the temperature range from 0.3 to 4.2 deg K, given temperature calibration data for a carbon resistance thermometer, experimental temperature drift, and heating period data. The speciftc heats calculated from these data are then fitted by a curve by the methods of least squares and the specific heats are corrected for the effect of the curvature of the data. The method, operation, program details, and program stop… more
Date: January 1, 1962
Creator: Roach, P.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING

Description: The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)
Date: December 12, 1961
Creator: Goodman, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flexible Monte Carlo Programs FMC-N and FMC-G

Description: Flexible Monte Carlo programs FMC-N and FMC-G (GE-ANPD Programs 516 and 515) are digital computer programs which apply Monte Carlo methods to simulate neutron and gamma ray life histories, respectively, in a source-shield configuration. The programs were designed for flexlbility in the geometrical, material, nuclear, and source descriptions of source-shield configurations and variance reduction techniques. The programs were also designed to optimize the use of fast memory and to provide complet… more
Date: April 28, 1961
Creator: Loechler, J. J. & MacDonald, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Algol Compiler for the Control Data Corporation 1604. Progress Report No. 2

Description: A summary of the progress on development of the ALGOL compiler for the Control Data Corporation 1604 Computer is presented. This computer is based on machine-independent specifications developed at ORNL. A brief description of the structure of the compiler is included along with discussions concerning language restrictions, the hardware language representation, and the required equipment configuration. An example illustrates the generated program instructions. (auth)
Date: October 18, 1962
Creator: Bumgarner, L. L.; Grau, A. A.; Lietzke, M. P.; Stueland, R. G. & Wolf, K. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROGRAM ODD--A ONE-DIMENSIONAL MULTIGROUP CODE FOR THE IBM-7090 (ANP PROGRAM NO. 657)

Description: The physical and mathematical reactor models which are used in Program ODD are discussed. In addition, the FORTRAN II source program listings, decimal data input sheets, and input and output for a sample case are given. Program ODD was designed to raake use of the Revised Nuclear Data System at ANPD which consists of twenty-five energy group cross-section data including high energy inelastic scattering matrices, resonance parameters for the resolved resonances, and thermalization scattering mat… more
Date: June 30, 1961
Creator: Fischer, P.G.; Wenstrup, F.D. & Hoffman, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source

Description: A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date: August 10, 1962
Creator: Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP Programs. M-1 Monte Carlo Radioisotope Shielding Code. Final Report

Description: The M-1 code is a Monte Carlo code that applies to cylindrical geometry when solving for the flux from a pre specified radiation source. The source is a gamma and beta emitter and the solution is for the flux of each energy group and of each region of interest in regard to the emitter. A region is a volume of the system bounded by two planes perpendicular to the axis of symmetry and two cylinders (one cylinder if the region includes the axis of symmetry). The code can be used to solve for a max… more
Date: May 1, 1962
Creator: Kniedler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TABLE OF TRIM DISCRETE QUADRATURE PARAMETERS FOR THIN BINARY SLAB CELLS

Description: Discrete quadrature weights and angles for use in discrete ordinate methods of solutions for thin cells were tabulated for a series of regional cell thicknesses of applicability. Parameters are given for 4, 8, 8, 10, and 12 angle approximations. The quadrature assignment was based upon a simplified integral transport solution to the spatial average of the angular distribution of uncollided flux, assuming flat sources. The quadrature assignments are designated TRIM, for thin-region integral meth… more
Date: September 1, 1962
Creator: Meneghetti, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gamma I. A General Theorem-Proving Program for the IBM 704

Description: GAMMA I is a FORTRAN-compiled program for the IBM 704 Electronic Data- Processing Machine. It embodies a certain general, uniform procedure H of mathematical logic for seeking out a proof of any theorem within any mathematical theory which is given in formal axiomatic form. An extended discussion is provided of the underlying method and of the necessary background of mathematical logic. The program is described in detail. (M.C.G.)
Date: November 1, 1961
Creator: Robinson, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AN INTRODUCTION TO 704 FORTRAN

Description: A fraction of the possibilities of Fortran are described, but at all times an effort was made to indicate where only a partial expose was made. Many specific examples are included to illustrate the word descriptions of Fortran programming. An appendix, which gives specific information concerning procedures relative to the use of the 704, is included. (auth)
Date: March 1, 1962
Creator: Pawlicki, G.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A TRANSLATOR-ORIENTED INTERMEDIATE COMPUTER LANGUAGE

Description: S>An intermediate language is described that was developed for the translation process for Algal programs and its requirements in terms of target language. The requirements made of the target language were that it be parenthesisfree, that it contain a minimum number of instruction types, and that it would simplify the translation process. The feasibility of this language as target language to simplify the machine translation process and the direct implementation of this language on a computer b… more
Date: May 1, 1962
Creator: Grau, A.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OGRE-P1, A Monte Carlo Program for Computing Gamma-Ray Transmission Through Laminated Slabs

Description: A Monte Carlo IBM-7090 program (OGRE-P1) was written for calculation of the dose rate on one side of a slab owing to an isotropic, cosine, or collimated monoenergetic gamma radiation source on the other side of the slab. A maximum of 50 homogeneous regions are permitted. (auth)
Date: May 23, 1962
Creator: Trubey, K. K.; Penny, S. K. & Emmett, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The modeling of complex continua: Fundamental obstacles and grand challenges. Annual progress report

Description: The research is divided into: discontinuities and adaptive computation, chaotic flows, dispersion of flow in porous media, and nonlinear waves and nonlinear materials. The research program has emphasized innovative computation and theory. The approach depends on abstracting mathematical concepts and computational methods from individual applications to a wide range of problems involving complex continua. The generic difficulties in the modeling of continua that guide this abstraction are multip… more
Date: January 1, 1993
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Using and programming the SUPERCODE

Description: SUPERCODE is a systems code used in designing tokamak devices and reactors. This report is divided into 4 chapters. Chapter one covers installing the code and directory organization. The execution of the code, command line editing and history, the shell language, classes, and shell input and output are discussed in chapter two. Chapter three covers the writing modules. In chapter four, the Consts module, Sys module, and Plot module are covered. At the end of the report, the need and use of SUPE… more
Date: June 8, 1994
Creator: Haney, S. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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