last modified: 01-MAR-1978 | catalog | categories | new | search |

PSR-0106 PLASMX.

PLASMX, MultiGroup Neutral Particle Transport in Tokamak CTR Plasma

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1. NAME OR DESIGNATION OF PROGRAM:  PLASMX.
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2. COMPUTERS
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Program name Package id Status Status date
PLASMX PSR-0106/01 Tested 01-MAR-1978

Machines used:

Package ID Orig. computer Test computer
PSR-0106/01 CDC 7600 CDC 7600
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3. DESCRIPTION OF PROBLEM OR FUNCTION

PLASMX provides multigroup cross sections for neutral hydrogen atom transport calculations in Tokamak-type CTR plasmas. These cross sections are written to tape in a format specifically tailored to the LASL neutron transport codes, but they can be written in any specific format.
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4. METHOD OF SOLUTION

PLASMX generates multigroup cross sections on one of the output files in a standard DTF-IV format suitable for one-and two-dimensional cylindrival discrete-ordinates transport codes, such a ONETRAN, TWOTRAN.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Variable
dimensioning presently restricts the number of energy groups to 22,  the number of spatial regions to 10, and the number of Legendre polynomial moments to 7 (P6). Changes for user applications are easily effected.
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6. TYPICAL RUNNING TIME

A two-group, two-region, P3 calculation requires approximately 30 s on a CDC-7600. An 11-group, 10-region, P3, calculation requires approximately 30 min.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
PSR-0106/01 01-MAR-1978 Tested at NEADB
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10. REFERENCES

- J.E. Morel and B.R. Wienke:
  "PLASMX: Multigroup Ionization and Charge Exchange Cross-Section
  Code for Neutral Hydrogen Transport in Plasmas",
  LA-6661-MS (January 1977).
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11. MACHINE REQUIREMENTS

A CDC computer with two system input/output units and two output disks or tapes are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0106/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Los Alamos National Laboratory, Los Alamos, New Mexico, USA
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16. MATERIAL AVAILABLE
PSR-0106/01
File name File description Records
PSR0106_01.001 INFORMATION 1
PSR0106_01.002 SOURCE PROGRAM (F4,EBCDIC) 1501
PSR0106_01.003 SAMPLE PROBLEM INPUT DATA 6
PSR0106_01.004 SAMPLE PROBLEM PRINTED OUTPUT 77
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • X. Magnetic Fusion Research

Keywords: cross sections, discrete ordinate method, fusion reactions, fusion reactors, hydrogen, multigroup, one-dimensional, plasma, thermonuclear reactions, transport theory, two-dimensional.