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TKO--A THREE-DIMENSIONAL NEUTRON-DIFFUSION CODE FOR THE IBM-704

Description: A description is given of a code for the IBM-704 computer which solves the few-group, time-independent, neutron-diffusion equations in x, y, z geometry. The number of lethargy groups may be one, two, three, or four, and the solution is obtained over a rectangular parallelepiped which is symmetric with respect to the plane x = y. A mesh of horizontal and vertical planes is imposed on this parallelepiped; all region interfaces must occur on mesh planes. Input parameters are specified regionwise, and completely variable mesh spacing is permitted. The number of mesh points on and to one side of the plane x = y is limited to 2675 and 4725 on 16,384-word and 32,768-word computers, respectively. Either a zero flux or a zero current boundary condition may be applied at each boundary limited to 2675 and 4725 on 16,384-word and 32,768-word computers, respectively. Either a zero flux or a zero current boundary condition may be applied at each boundary plane. The code was constructed to provide great ease of input preparation and simplicity of code operation. The running time of a typical two-group, 2600-point problem is 1.5 hours. (auth)
Date: October 1, 1959
Creator: Cadwell, W.R.
Partner: UNT Libraries Government Documents Department

Fortran Programming Techniques for Graph Plotting on the IBM-704 Computer

Description: The numerical results of the IBM-704 computer can be put into graphieal form with the aid of the IBM-717 peripheral line printer, and programming techniques using FORTRAN II are described for the production of several kinds of graphs. Different symbols can be used, and a total of 100 horizontal spaces are available, giving a resolution of 1%. (D.L.C.)
Date: May 1, 1960
Creator: Cohn, C. E.
Partner: UNT Libraries Government Documents Department

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

ECOLOGICAL SAMPLING AND METEOROLOGICAL CALCULATION OF FALLOUT ON FORESTS NEAR OAK RIDGE

Description: Spatial patterns of radioactive contuamination on forest foliage were measured by gamma spectrometry and are discussed with respect to local vs. world- wide origin of the fallout and implications for ecology, health physics, and management of nuclear facilities. In September 1959, I/sup 131/ on dogwood leaf samples varied from over 500 mu mu c/g dry wt near Oak Ridge National Laboratory stacks to 1 to 7 mu mu c/g near the margins of the Oak Ridge Reservation. Stack fallout tended to occur closer to the source than was calculated from hourly wind data by an IBM 610 computer program based on Culkowski' s adaptation of the SuttonChamberlain theory of atmospheric diffusion and deposition. Over most of the Reservation levels of Ru/sup 106/ Cs/sup 137/ Zr/sup 9/ >s/sup 5/Nb/sup 95/ and Ce/sup 144/ were similar to levels found elsewhere (2 to 9, 1 to 3, 2 to 9, and 10 to 20 mu mu c/g respectively) and were presumably controlled by weapons fallout. Higher levels were found in small areas and indicate the need for attention to localized contamination, even though indirect estilevels considered hazardous from the standpoint of health physics. (auth)
Date: September 20, 1961
Creator: Olson, J.S.
Partner: UNT Libraries Government Documents Department

Automatic Tester for Electrical Fuses

Description: Abstract: This technical memorandum describes an automatic tester and recorder as it is used in obtaining fusing time information from electrical fuses for subsequent analysis in the IBM 704 computer.
Date: November 1961
Creator: Longerot, Carl D.
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

SPAN-2--AN IMB-704 CODE TO CALCULATE UNCOLLIDED FLUX OUTSIDE A CIRCULAR CYLINDER

Description: The SPAN-2 code calculates the uncollided gamma flux at a point outside a right circular cylinder which is surrounded by cyllndrical shell shields and above which are plane slab shields. The cylinder is assured to contain a source of gamma radiation which varies in the radial and axial directions only. Field points may be located in a plane through the axis of the cylinder. The method of integration used is three-dimensional Gaussian quadrature. Typical computing and editing time for a 20 field point problem, in which there are 10 side and 10 top shields, is four minutes per energy level. A 32,768 word IBM-704 is required for the code. (auth)
Date: August 1, 1959
Creator: Gillis, P.A.; Lawton, T.J. & Brand, K.W.
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

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.
Partner: UNT Libraries Government Documents Department

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.
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 General 704 Service Library

Description: A unified set of input, output, and diagnostic routines for the Argonne IBM 704 digital computer is described. The library is designed to give maximum ease in programming the input and output functions required by a program. lt also provides for rapid execution of diagnostic and emergency dumps. (M.C.G.)
Date: March 1, 1962
Creator: Bagus, P. S.; Roothaan, C. C. J.; Worley, W. S., Jr. & Wunderlich, M. C.
Partner: UNT Libraries Government Documents Department

ATBAC CHECK CALCULATION ON THE IBM 650, PROGRAM NO. 303

Description: This program, using the lBM 650 electronic data processing machine, is used primarily as a tool in order to prepare input data for an lBM 704 code ATBAC. The code calculates steady state thermal characteris tics of a plate type fuel element for both a nominal and adverse chanael. (auth)
Date: March 13, 1959
Creator: Beretsky, I. & Oby, P.V.
Partner: UNT Libraries Government Documents Department

SLOP-1, A THERMAL MULTI-GROUP PROGRAM FOR THE IBM-704

Description: SLOP-I, a thermal multi-group program written for the IBM-704, is discussed. It was used extensively to test the utility of various H/sub 2/O scattering kernels, and to assess the accuracy of other computing methods. The problems solved by the code, the physical approximations in the program and library, the method of solution, and suggested modes of operation are described. Derivaticns of all basic equations and complete input and running instructions are included. (M.C.G.)
Date: October 1, 1960
Creator: Bohl, H.; Gelbard, E.; Buerger, P. & Culpepper, G.
Partner: UNT Libraries Government Documents Department

DETERMINATION OF LATTICE PARAMETERS WITH THE AID OF A COMPUTER. Final Report of Metallurgy Program 4.1.8.

Description: The detemnination of precision lattice parameters using a least-squares analytical treatment has been programmed into a computer. Although it was originally coded for the Argonne AVIDAC and GEORGE computers, it is now programmed for the IBM 704. The present program permits the determination of lattice parametsrs and standard errors for the orthorhombic system and for all other crystal systems of higher symmetry. The angular measurements of line positions from a Debye-Scherrer or symmetrical focusing camera or a diffractometer may be given in degrees or radians from several different wavelengths. Provision was made for using aa many as three separate correction terms for eccentricity, absorption, divergence, and others; however, one, two, three, or none at all, may be used. The exact trigonometric function or functions used in these correction terms may be selected from several of those previously suggested. If desired, a weighting factor may also be used for each reflection which may include an observation weight or trigonometric function or both. Examples will be given of lattice parameters obtained for various crystal systems using different correction terms with and without weighting. (auth)
Date: January 1961
Creator: Mueller, M. H. & Heaton, L.
Partner: UNT Libraries Government Documents Department

Ax-1, a Computing Program for Coupled Neutronics-Hydrodynamics Calculations on the Ibm-704

Description: The presentation includes a very general outline of the program, a semi- detailed flow diagram which emphasizes the physics and control aspects of the calculation, and then a detailed flow diagram and listing of the program (which is written in Fortran). Explanatory notes accompany thc diagrams. Following the notes on the program, master lists detailing thc roles of the sense switches, sense lights, pauses, and stops are presented. The operating instructions are then given, followed by a sample problem, including detailed information on input data. The theoretical discussion has been kept primarily in the appendices, and is generally in outline form with references, rather than in full exposition. (auth)
Date: May 1, 1959
Creator: Okrent, D.; Cook, J. M.; Satkus, D.; Lazarus, R. B. & Wells, M. B.
Partner: UNT Libraries Government Documents Department

THERMAL FLUX PROGRAM FOR A SLAB SYSTEM

Description: A program is described for computing a quantity, Q, proportional to the neutron scalar flux, in an infinite heterogeneous slab system. The system is generated by a two-region unit cell. Q is the average track length per unit length, in a given interval, arising from the neutron traffic established by a spatially distributed monenergetic source. The program is coded for the IBM 704 computer. (auth)
Date: February 1, 1958
Creator: Beeler, J.R. & Popp, J.D.
Partner: UNT Libraries Government Documents Department