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Browsing Scientific and Technical Reports by Subject "A codes"

Now showing 1 - 12 of 12
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    AEJCL: a JCL syntax checking facility
    (Australian Atomic Energy Commission, 1973-02) Hayes, IJ
    AEJCL provides a listing and JCL syntax checking facility on a PDP/9L computer system. The syntax checking system is controlled by a directed graph structure which is initially written in a machine independent language and then translated to PDP/9L code automatically. The input and output sections of the system are handled asynchronously by a multitasking master control program.
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    AESYNTAX: a FORTRAN syntax analysis system for the PDP9L
    (Australian Atomic Energy Commission, 1972-12) Barry, JM
    A facility is presented to assist FORTRAN programmers in the development of new programs by the immediate listing and syntax analysis of FORTRAN coded source decks independently of the central computer.
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    AEUPDATE - an editor designed to allow sequential and partitioned data sets to be updated
    (Australian Atomic Energy Commission, 1973-08) Johnstone, IL
    The implementation and use of an editor developed for the IBM360 Operating System is described. The editor provides the capability to update both sequential and partitioned data sets as well as providing facilities for printing or punching all or parts of data sets. A feature of this editor is the ability to use many data sets for input or output during update operations. The editor is more versatile and less complicated to use than the editors supplied with the Operating System.
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    Analysis of power transients observed in spert i reactors, Part 1 - transients in aluminium plate-type reactors initiated at ambient temperature
    (Australian Atomic Energy Commission, 1975-03) Clancy, BE; Connolly, JW; Harrington, BV
    An investigation of SPERT I reactor reactivity feedback mechanisms has been made using the modular code AUS. Feedback terms so obtained have been used in the transient analysis code ZAPP to calculate transient behaviour for step and ramp reactivity additions. A simple model of coolant boiling has been used to analyse transients for which cladding temperatures exceed the saturation temperature of water. The generally good agreement obtained with experimental data supports the case that core only temperature coefficients are much larger than those obtained by heating core and reflector.
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    Analysis of pulse height spectra from an organic scintillator spectrometer
    (Australian Atomic Energy Commission, 1980-07) Whittlestone, S
    A suite of three computer codes has been written to analyse the pulse height spectra from an organic scintillator neutron or gamma ray spectrometer. Data prepared by the first code are submitted to the second which unfolds the pulse height spectra. Comparison and presentation of analysed data are performed by the third code. The spectrum unfolding process was tested by unfolding the fairly complex spectrum from the 9Be(d,n)10B reaction, which was known from other measurements. The performance of the code when unfolding monoenergetic neutron responses was comparable to the performance of codes used by other workers.
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    ANAUSN - a one-dimensional multigroup SN transport theory module for the AUS reactor neutronics system.
    (Australian Atomic Energy Commission, 1982-05) Clancy, BE
    ANAUSN is a general purpose one-dimensional discrete ordinate transport theory program which has access to AUS datapools. Fixed source reactivity and a variety of criticality search calculations can be performed. The program can be operated as a module in the AUS scheme or as a stand-alone program.
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    AUS - the Australian modular scheme for reactor neutronics computations
    (Australian Atomic Energy Commission, 1975-12) Robinson, GS
    A general description is given of the AUS modular scheme for reactor neutronics calculations. The scheme currently includes modules which provide the capacity for lattice calculations, ID transport calculations, 1 and 2D diffusion calculations (with feedback—free kinetics), and burnup calculations. Details are provided of all system aspects of AUS, but individual modules are only outlined. A complete specification is given of that part of user input which controls the calculation sequence. The report also provides sufficient details of the supervisor program and of the interface data sets to enable additional modules to be incorporated in the scheme.
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    AUS burnup module char and the associated status data pool
    (Australian Atomic Energy Commission, 1975-12) Robinson, GS
    The CHAR module of the AUS reactor neutronics scheme solves the multiregion nuclide depletion equations using an analytic method. The module obtains cross section, flux and geometry data from AUS data pools, and uses the STATUS data pool which has been designed for the storage of nuclide compositions, spatial smearing factors and other miscellaneous information.
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    AUS model AUSED - an editing program for AUS cross section data pools
    (Australian Atomic Energy Commission, 1976-05) Harrington, BV
    AUSED is a loading and editing module for AUS cross section data pools and is part of the AUS modular code scheme for reactor systems. The fitting of subgroup parameters for the resonance theory of the module MIRANDA has been included as an option. Emphasis has been placed on flexibility and free format style input.
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    IBM360 and NOVA software developed to allow plotter output to be displayed on the Tektronix T4002 graphical display terminal
    (Australian Atomic Energy Commission, 1973-06) Backstrom, RP; Sanger, PL
    The interaction of IBM360 programs with the Tektronix T4002 Graphical Display terminal attached to the NOVA computer is described. These interactive facilities are used to allow plotter output from the IBM360 computer to be displayed on the Tektronix Display Screen. Arbitrary sections of plots may be enlarged to any desired magnification for detailed viewing without the traditional 'wrap-around' problem. This application is the first example of interactive computing using the AAEC Network and demonstrates the effectiveness of both the hardware and the software involved.
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    IBM360 and NOVA software developed to give the NOVA computer access to the resources of the IBM360 computer
    (Australian Atomic Energy commission, 1973-06) Sanger, PL; Backstrom, RP
    IBM360 and NOVA software to allow NOVA programs stored as load modules on IBM360 disk storage to be loaded directly into the NOVA computer via the Dataway, and to allow the contents of NOVA core storage to be sent to the IBM360 computer and listed on the IBM1403 line printer, is described. This software can be used as the basis for the development of software to allow other Dataway computers to access the IBM360 computer. A scheme for adding interactive programs to the normal IBM360 Jobstream by writing the necessary JCL and SYSIN data to the HASP internal reader is also presented.
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    Macros to simulate FORTRAN I/O in assembler programs
    (Australian Atomic Energy Commission, 1972-12) Johnson, SG
    The AREAD, AWRITE, AFORMAT, ABACKSP, AREWIND and AENDPILE instructions are described. They are analogous to the FORTRAN READ, WRITE, FORMAT, BACKSPACE, REWIND and END FILE statements respectively and are intended for use by FORTRAN programmers when writing in the IBM System 360 assembler language.