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Differences between LASL- and ANL-processed cross sections. [MINX/1DX vs ETOE-2/MC/sup 2/-2]

Description: As part of the Los Alamos Scientific Laboratory (LASL) cross-section processing development, LASL cross sections and results from MINX/1DX system are compared to the Argonne National Laboratory cross sections and results from the ETOE-2/MC/sup 2/-2 system for a simple reactor problem. Exact perturbation theory is used to establish the eigenvalue effect of every isotope group cross-section difference. Cross sections, cross-section differences, and their eigenvalue effects are clearly and conveni… more
Date: March 1, 1978
Creator: Kidman, R. B.; MacFarlane, R. E. & Becker, M.
Partner: UNT Libraries Government Documents Department
open access

Isotopic safeguards data bank (ISTLIB) and control program (MISTY). [MISTY]

Description: As part of the U.S. program to provide technical assistance to the International Atomic Energy Agency (IAEA), the Pacific Northwest Laboratory (PNL) has developed a computer code and data bank to aid in the safeguards verification of spent fuel content at the head end of a reprocessing facility. A description and user instructions that uses isotopic safeguards techniques are presented for MISTY, a computer program for analyzing an isotopic data base (ISTLIB). The input, operating procedures, an… more
Date: September 1, 1978
Creator: Timmerman, C. L.
Partner: UNT Libraries Government Documents Department
open access

MAGIC: a one-dimensional magneto-inductive particle code. [In FORTRAN for DEC 10 computers]

Description: MAGIC, a new one-dimensional particle code, simulates magneto-inductive phenomena in a cylindrically symmetric magnetized plasma. The physical model and the computational algorithm used for the code are described. A user's guide to and a listing of MAGIC are also included.
Date: May 23, 1978
Creator: Brengle, T.A. & Cohen, B.I.
Partner: UNT Libraries Government Documents Department
open access

Application of artificial intelligence techniques to the acceleration of Monte Carlo transport calculations. [Application to MCN code]

Description: The techniques of learning theory and pattern recognition are used to learn splitting surface locations for the Monte Carlo neutron transport code MCN. A study is performed to determine default values for several pattern recognition and learning parameters. The modified MCN code is used to reduce computer cost for several nontrivial example problems.
Date: September 1, 1978
Creator: Maconald, J.L. & Cashwell, E.D.
Partner: UNT Libraries Government Documents Department
open access

MAGIC: a one-dimensional magneto-inductive particle code

Description: MAGIC, a new one-dimensional particle code, simulates magneto-inductive phenomena in a cylindrically-symmetric magnetized plasma. We describe the physical model and the computational algorithm used for the code. A user's guide to and a listing of MAGIC are also included.
Date: July 18, 1978
Creator: Brengle, T.A. & Cohen, B.I.
Partner: UNT Libraries Government Documents Department
open access

Computations of Nuclear Response Functions with MACK-IV

Description: The MACK computer program calculates energy pointwise and multigroup nuclear response functions from basic nuclear data in ENDF/B format. The new version of the program, MACK-IV, incorporates major developments and improvements aimed at maximizing the utilization of available nuclear data and ensuring energy conservation in nuclear heating calculations. A new library, MACKLIB-IV, of nuclear response functions was generated in the CTR energy group structure of 171 neutron groups and 36 gamma gro… more
Date: 1978-21~
Creator: Abdou, M. A. & Gohar, Y.
Partner: UNT Libraries Government Documents Department
open access

MC6800 cross-assembler for the PDP-8/E digital computer. [M68CA]

Description: A cross-assembler was developed to assemble Motorola MC6800 microprocessor programs on a digital Equipment Corporation PDP-8/E minicomputer. This cross-assembler runs in 8K of core under the OS/8 operating system. The advantages of using the cross-assembler are the large user symbol table and the convenience and speed of program development. User's instructions for the cross-assembler are given. The design of the cross-assembler and examples of its use are described. 12 figures.
Date: August 1, 1978
Creator: Sand, R.J.
Partner: UNT Libraries Government Documents Department
open access

Matpro--version 10: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior

Description: The materials properties correlations and computer subcodes (MATPRO--Version 10) developed for use with various LWR fuel rod behavior analytical programs at the Idaho National Engineering Laboratory are described. Formulations of fuel rod material properties, which are generally semiempirical in nature, are presented for uranium dioxide and mixed uranium--plutonium dioxide fuel, zircaloy cladding, and fill gas mixtures.
Date: February 1, 1978
Creator: Reymann, G.A. (comp.)
Partner: UNT Libraries Government Documents Department
open access

MACKLIB-IV: A Library of Nuclear Response Functions Generated With the MACK-IV Computer Program From ENDF/B-IV

Description: MACKLIB-IV employs the CTR energy group structure of 171 neutron groups and 36 gamma groups. A retrieval computer program is included with the library to permit collapsing into any other energy group structure. The library is in the new format of the ''MACK-Activity Table'' which uses a fixed position for each specific response function. This permits the user when employing the library with present transport codes to obtain directly the nuclear responses (e.g. the total nuclear heating) summed … more
Date: March 1, 1978
Creator: Gohar, Y. & Abdou, M. A.
Partner: UNT Libraries Government Documents Department
open access

MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format

Description: MACK-IV calculates nuclear response functions important to the neutronics analysis of nuclear and fusion systems. A central part of the code deals with the calculation of the nuclear response function for nuclear heating more commonly known as the kerma factor. Pointwise and multigroup neutron kerma factors, individual reactions, helium, hydrogen, and tritium production response functions are calculated from any basic nuclear data library in ENDF/B format. The program processes all reactions in… more
Date: July 1, 1978
Creator: Abdou, M. A.; Gohar, Y. & Wright, R. Q.
Partner: UNT Libraries Government Documents Department
open access

Computer mapping software at the Lawrence Berkeley Laboratory. [MAPEDIT, ZINC, CARTE, IDDS, GRAFPAC, in FORTRAN for CDC computers]

Description: A number of FORTRAN programs useful for computer mapping are supported by the Computer Science and Applied Mathematics Department for preparing base files and displays of statistical data. Digitizing and editing of geographic base files is maintained by the programs MAPEDIT and ZING. Display of statistical attributes of discrete points, lines, or areas in two dimensions is done by the program CARTE. Display in three dimensions or of surfaces is accomplished using subroutines from the Integrated… more
Date: June 1, 1978
Creator: Wood, P.M. & Benson, W.H.
Partner: UNT Libraries Government Documents Department
open access

Effects of the SSRL wiggler on the SPEAR beam

Description: A wiggler for SSRL has been built, is now undergoing magnetic testing, and is scheduled to be installed in SPEAR in time for the October turn-on. This wiggler is a 7-pole (5 full- and 2 half-pole), 3-period design, approximately 1 m effective length, and designed to reach 18 kG peak field. It will be placed in the short straight section just counterclockwise from the south symmetry point. In this note, the effects of this wiggler on the beam are estimated by means of the computer program MAGIC … more
Date: July 1, 1978
Creator: Helm, R.H.
Partner: UNT Libraries Government Documents Department
open access

MACK/MACKLIB System for Nuclear Response Functions

Description: The MACK computer program calculates energy pointwise and multigroup nuclear response functions from basic nuclear data in ENDF/B format. The new version of the program MACK-IV, incorporates major developments and improvements aimed at maximizing the utilization of available nuclear data and ensuring energy conservation in nuclear heating calculations. A new library, MACKLIB-IV, of nuclear response functions was generated in the CTR energy group structure of 171 neutron groups and 36 gamma grou… more
Date: March 15, 1978
Creator: Abdou, M. A. & Gohar, Y. M.
Partner: UNT Libraries Government Documents Department
open access

MCOCO: a computer program for seismic analysis of the HTGR core. Volume I. User's and theoretical manual

Description: This report presents documentation of the MCOCO (Multiple COre COlumn) computer program. The program was generated to perform dynamic analysis on a gas-cooled reactor core, which, structurally, is not only nonlinear, but also discontinuous. The report may be used as both a theoretical and user's manual for the MCOCO code. Input for the program consists of geometric and dynamic data (mass, spring constants, etc.). Output includes dowel forces, element collision forces, spring pack forces and cor… more
Date: April 1, 1978
Creator: Thompson, R.W.
Partner: UNT Libraries Government Documents Department
open access

Code Development and Analysis Program: developmental checkout of the BEACON/MOD2A code. [PWR]

Description: A best-estimate transient containment code, BEACON, is being developed by EG and G Idaho, Inc. for the Nuclear Regulatory Commission's reactor safety research program. This is an advanced, two-dimensional fluid flow code designed to predict temperatures and pressures in a dry PWR containment during a hypothetical loss-of-coolant accident. The most recent version of the code, MOD2A, is presently in the final stages of production prior to being released to the National Energy Software Center. As … more
Date: December 1, 1978
Creator: Ramsthaler, J. A.; Lime, J. F. & Sahota, M. S.
Partner: UNT Libraries Government Documents Department
open access

Application of Principal Components Analysis (PCA) for long-term assessment of operating releases from the nuclear power industry

Description: The application of the Principal Components Analysis (PCA) methodology to the long-term assessment of operating releases from the nuclear power industry was investigated. Gaussian calculations had been previously compared with MATHEW/ADPIC calculations for a simulated 24-hr release in the Hudson River Valley and an area in the southeast. Considerable differences were noted in the comparisons, which were attributed to the more realistic simulation of the time and space varying wind fields by the… more
Date: November 1, 1978
Creator: Dickerson, Marvin H.; Walton, John J. & Tuerpe, Dieter R.
Partner: UNT Libraries Government Documents Department
open access

ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing

Description: The ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing codes were designed to provide a comprehensive neutron cross-section processing capability for a wide range of applications including critical experiment analysis and core design calculations. Fundamental nuclear data from ENDF/B provide the primary input to the code system, and the output consists of a user-specified CCCC ISOTXS multigroup cross-section data file. Great flexibility is provided to the user in specifying the rigor of… more
Date: January 1, 1978
Creator: Toppel, B. J.; Henryson, H., II & Stenberg, C. G.
Partner: UNT Libraries Government Documents Department
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