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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.
Partner: UNT Libraries Government Documents Department

ZORCH--AN IBM 7090 PROGRAM FOR THE ANALYSIS OF SIMULATED MSRE POWER TRANSIENTS WITH A SIMPLIFIED SPACE-DEPENDENT KINETICS MODEL

Description: A program (ZORCH) is described which is an extended and revised version of the point-model kinetics program MURGATROYD. A model is used in which the axial space dependence of the fuel and graphite temperatures is calculated, and the effect on reactivity of deviations from the steady state values is assumed to be given by the product of an appropriate temperature coefficient of reactivity times the deviations from the steady state value of the nuclear average temperature (NAT). The NAT is computed using a sine-squared'' weighting function in the axial direction and using an input weighting factor in the radial direction. The shape of the power density is taken to be - time- independent in contrast to the shapes of the temperature distributions, which are time-dependent in the calculation. This program is intended to be used in surveys of reactor behavior under a wide range of conditions. It is therefore based on a simplified model in order to reduce computing time, but should provide a better approximation to reactor behavior than does a purely space-independent calculation. A derivation of the equations used in the program, instructions for its use, and sample input and output for a test case are included. A FORTRAN source deck and a binary object deck are on file. (auth)
Date: September 18, 1962
Creator: Nestor, C.W. Jr.
Partner: UNT Libraries Government Documents Department

AN ALGOL 60 SYNTAX CHECKER FOR THE IBM 7090 COMPUTER

Description: A syntax checker was designed based on the syntax of Algol as previously described. It was desirable to design the syntax checker as a set of mutually recursive processors tied together by building blocks which perform certain bookkeeping functions. Because of the recursive nature of the language and of the syntax checker, the problem of recovery after an error required much attention. A method was devised which permits most programs to be checked completely despite errors. The syntax checker was implemented for the IBM 7090 as a part of the SHARE ALGOL processor, and has operated very satisfactorily. (auth)
Date: March 21, 1963
Creator: Lietzke, M.P.
Partner: UNT Libraries Government Documents Department

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 basis. (auth)
Date: October 17, 1962
Creator: Prince, C.E. & Milford, R.P.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

POLFIT II, AN IBM 7090 PROGRAM FOR POLYNOMIAL LEAST SQUARES FITTING

Description: A program was written to perform polynomial least squares fits on the IBM 7090 computer. Weighting factors may be included with the data if desired. The program includes a subroutine which does the fit and furnishes the calling program with the coefficients, standard errors in the coefficients, staandard error of fit, and information necessary to compute a complete error analysis; and a calling program which reads input, calls the subroutine, and writes requested output. The subroutine may be used separately in any Fortran or FAP program where a least squares fit is needed. (auth)
Date: April 24, 1961
Creator: Lietzke, M.P.
Partner: UNT Libraries Government Documents Department

WHIRLAWAY--A THREE-DIMENSIONAL, TWO-GROUP NEUTRON DIFFUSION CODE FOR THE IBM 7090 COMPUTER

Description: WHIRLAWAY is an IBM 7090 FORTRAN programmed code for the solution of two- group neutron diffusion equations in xyz geometry. The code was designed to run under control of the IBM 7090 FORTRAN Monitor System on a machine with at least six tape units. The maximum number of mesh points is limited to 12,750. Arbitrary distributions of materials and mesh spacing are permitted. The boundary conditions are either zero flux or zero current at each of the six faces of the reactor, and the code will, if desired, compute the adjoint-flux and associated flux-adjoint-flux region integrals that are necessary for perturbation calculations. Computation time is approximately 0.006 sec per point iteration. Normally, running times are about 2 to 3 hr for a 10,000-point problem. (auth)
Date: August 15, 1961
Creator: Fowler, T. B. & Tobias, M. L.
Partner: UNT Libraries Government Documents Department

AXIAL TEMPERATURE AND PRESSURE DISTRIBUTION IN EGCR. DEVELOPMENT OF THE PTD-1 PROGRAM

Description: The equations and procedures of the PTD-1 program for obtaining the surface temperature distribution, the gas bulk temperature, and the pressure distribution for any of the 234 channels in the EGCR are developed. The program, in FORTRAN for the IBM 7090, is designed for any arbitrary power distribution yielding a constant gas outiet temperature or a given maximum surface temperature and includes the effects of thermal radiation on surface and bulk gas temperatures. The flow sheet and some results are included. (auth)
Date: February 18, 1964
Creator: Robinson, J.C. & Lence, J.T.
Partner: UNT Libraries Government Documents Department

NEUTRON THERMALIZATION PROGRAMS FOR THE IBM 7090

Description: A system of six codes is described that permits the solution of a broad class of problems encountered in the study of neutron thermalization, average cross sections, and spectral models. These programs are all compatible with use on MONITOR for the IBM 7090. The Fortran listings are given. (auth)
Date: February 25, 1963
Creator: Preskitt, C.A.; Nephew, E.A. & Tsagaris, M.E.
Partner: UNT Libraries Government Documents Department

MIST--BUBBLE CHAMBER DATA REDUCTION PROGRAM

Description: MIST is an IBM 7090 program prepared at Brookhaven National Laboratory as part of a cooperative effort for bubble chamber data processing. The program reads the prepared data and outputs it on magnetic tape in a suitable format for input to the Haze-Fog-Cloudy-Fair Programs used with a flying spot digitizer. MIST deletes erroneous data, edits, sequences, and supplies additional physical data not digitized. MIST also prepares detailed summaries and statistics for the events processed and checks digitizer operation. (H.G.G.)
Date: February 1, 1963
Creator: Friedman, J.M.
Partner: UNT Libraries Government Documents Department

INTRIGUE, AN IBM-7090 SUBROUTINE PACKAGE FOR MAKING LINEAR, LOGARITHMIC AND SEMILOGARITHMIC GRAPHS USING THE CALCOMP PLOTTER

Description: An IBM-7090 subroutine package has been written to facilitate the plotting of curves and points on linear, logarithmic, and semilogarithmic graphs using the CALCOMP plotter. The subroutines accomplish the necessary computations and prepare a magnetic tape for use by the plotter. (auth)
Date: March 1, 1964
Creator: Emmett, M.B.
Partner: UNT Libraries Government Documents Department

COMPUTER PROGRAMS USING ZONAL HARMONICS FOR MAGNETIC PROPERTIES OF CURRENT SYSTEMS WITH SPECIAL REFERENCE TO THE IBM 7090

Description: The magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident are discussed. Each system may include a combination of coaxial loops, cylindrical or plane annular current sheets, and cylindrical coils of rectagular section. Working equations are listed, following an outline of theory. A discussion of errors and of means for reducing them leads to specific suggestions ior use of the method with any programmed computer. An existing comprehensive program for the IBM 7090 is described in detail. The rate of convergence of the harmonic series depends on the ratio R of the polar radius of the field point to that of the current discontinuity nearest the origin. In some cases the precision reaches 1000 parts per million even at R = 0.95, improving to 1 or 2 parts at R = 0.80. Since the origin is arbitrary, the practical range of the method often includes the whole space that is accessible to experiment. For very close approach to the windings one must resort to elliptic integrai methods or their equivalent. Alternative programs that were previously used are compared with the method of zonal harmonics, but they are slower by more than a factor of 10 when large numbers of field calculations must be made on a complex curCent system. One example is the problem of following individual ions through paths in the order of 100 turns in a field that is generated by 20 coaxial thick coils; available competing methods would have required too much computer time. The zonal harmonlc method also has superior flexibility in attacking a wide range of problems. This is especially true for the calculation of rates of ...
Date: December 1, 1962
Creator: Garrett, M.W.
Partner: UNT Libraries Government Documents Department

THE SOLUTION OF THE GENERAL LEAST SQUARES PROBLEM WITH SPECIAL REFERENCE TO HIGH-SPEED COMPUTERS

Description: This report extends and revises LA-2387. Changes in the Los Alamos non- linear least squares program are outlined. A condensed guide for the data card arrangement is presented. The PAKAG code is written in FORTRAN language for the IBM-7090. The system fits a given function to a given data set. The function to be fitted can be any well-behaved'' mathematical function for which the derivatives exist and for which the data set does not give rise to points of singularity. (M.C.G.)
Date: November 1, 1962
Creator: McWilliams, P.
Partner: UNT Libraries Government Documents Department

IBM-7090 PROGRAMS TO COMPILE AND MODIFY A NUCLEAR DATA TAPE

Description: The Reactor Nuclear Data Tape Programs were designed to compile and/or modify a nuclear data library tape from basic nuclear cross-section input. It is intended that this cross-section library tape will be utilized to provide up-to- date nuclear data for various reactor codes. Program RNDP was designed to compile an initial tape from certain minimal input data, or to add or delete complete blocks of data from an existing tape. Program RNDM was designed to compile and add to an existing tape macroscopic cross section data consisting of mixtures of microscopic cross sections available on the tape. Program RNOC was designed to modify and copy an existing tape, or to compile a new tape from sets of binary cards punched by Program RNDP. These programs were written using the FORTrAN-II system of automatic coding for the IBM7090. (auth)
Date: May 31, 1961
Creator: Herrmann, R.G.; Hoffman, T.A.; Wenstrup, F.D. & Wilcox, A.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth)
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Partner: UNT Libraries Government Documents Department

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 built into the code, and results may be obtained by using either or both methods. An IBM 7090 computer wtth seven tape untts is required. Computations are performed at the approximate rate of l0,000/n mesh points per minute, where n is the number of axial, radial, and angular increments. The program is run under the control of the IBM 7090 MONITOR system. (auth)
Date: February 26, 1962
Creator: Tobias, M.L.; Vondy, D.R. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department

THE TWENTY GRAND PROGRAM FOR THE NUMERICAL SOLUTION OF FEW-GROUP NEUTRON DIFFUSION EQUATIONS IN TWO DIMENSIONS

Description: The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are available. Normalization of fluxes to an arbitrary input power is allowed. The fission source distribution and the adjoint fluxes and associated integrals may be computed at the user's option. The number of mesh sweeps permitted is stated as input. The average running time in seconds per iteration per group is approximately 0.0035. (auth)
Date: February 21, 1962
Creator: Tobias, M.L. & Fowler, T.B.
Partner: UNT Libraries Government Documents Department