Computer Programs
NEA-1151 SUSD.
last modified: 06-DEC-1991 | catalog | categories | new | search |

NEA-1151 SUSD.

SUSD, Sensitivity and Uncertainty in Neutron Transport and Detector Response

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1. NAME OR DESIGNATION OF PROGRAM:  SUSD.
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2. COMPUTERS
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Program name Package id Status Status date
SUSD NEA-1151/03 Tested 06-DEC-1991

Machines used:

Package ID Orig. computer Test computer
NEA-1151/03 HITAC M-150 H Many Computers
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SUSD calculates sensitivity coefficients for one and two-dimensional transport problems. Variance and standard deviation of detector responses or design parameters can be obtained using cross-section covariance matrices.  In neutron transport problems, this code is able to perform sensitivity-uncertainty analysis for secondary angular distribution  (SAD) or secondary energy distribution (SED).
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4. METHOD OF SOLUTION

The first-order perturbation theory is used to  obtain sensitivity coefficients. The method described in the distributed report is employed to consider SAD/SED effect.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Variable dimension is used so that there is no limitation in each array size but the total core size.
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6. TYPICAL RUNNING TIME

It depends on type, dimension and size of problems to be solved.
NEA-1151/03
This revised version of the code has only been compiled by NEA-DB on IBM 3090 and VAX 8810 computers. No test cases were available for execution.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

GROUPSR: An additional code module for the NJOY code system to prepare partial cross sections for SAD sensitivity analysis.
SEADR: An additional code module for the NJOY code system to prepare group group covariance matrices for SAD/SED uncertainty analysis.
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9. STATUS
Package ID Status date Status
NEA-1151/03 06-DEC-1991 Tested at NEADB
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10. REFERENCES:
- R.E. MacFarlane, et al.:, LA-7584-M(1978)
NEA-1151/03, included references:
- K. Furta, Y. Oka and S. Kondo:
  SUSD: A Computer Code for Cross-Section Sensitivity and
  Uncertainty Analysis including Secondary Neutron Energy and
  Angular Distributions
  Draft of UTNL-R0185 (English Translation, August 1986)
- I. Kodeli:
  Modifications to SUSD Code (July 1991)
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11. MACHINE REQUIREMENTS

Core requirements depend on problem complexity, but most problems may be executed within 1 Mbytes. Up to 10 disk or tape devices are required in addition to the standard input and output devices.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1151/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-1151/03
MVS/XA with VS FORTRAN LEVEL 2.1.1 compiler (IBM 3090); VMS V5.0 with VAX FORTRAN V5.0-1 compiler (VAX 8810).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

     Lazuo FURUTA, Shunsuke KONDO, Yoshika OKA
     Faculty of Engineering
     University of Tokyo, Japan
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16. MATERIAL AVAILABLE
NEA-1151/03
File name File description Records
NEA1151_03.001 INFORMATION FILE 327
NEA1151_03.002 CONVERSION PROGRAM SOURCE 7
NEA1151_03.003 NJOY MAIN SOURCE CODE FOR IBM 2700
NEA1151_03.004 GROUPSR SOURCE CODE FOR IBM 4979
NEA1151_03.005 SEADR SOURCE CODE FOR IBM 1830
NEA1151_03.006 SUSD SOURCE CODE FOR IBM 2618
NEA1151_03.007 JCL USED AT NEADB TO RUN THE PACKAGE ON IBM 493
NEA1151_03.008 ORIGINAL JCL TO RUN GROUPSR CODE (IBM) 19
NEA1151_03.009 ORIGINAL JCL TO RUN SEADR CODE (IBM) 16
NEA1151_03.010 ORIGINAL JCL TO RUN SUSD CODE (IBM) 15
NEA1151_03.011 NJOY MAIN SOURCE FOR VAX 2700
NEA1151_03.012 GROUPSR SOURCE CODE FOR VAX 4982
NEA1151_03.013 SEADR SOURCE CODE FOR VAX 1828
NEA1151_03.014 SUSD SOURCE CODE FOR VAX 2619
NEA1151_03.015 VAX COMMAND PROCEDURE 67
NEA1151_03.016 FORWARD ANGULAR FLUX 2604
NEA1151_03.017 ADJOINT ANGULAR FLUX 2604
NEA1151_03.018 GROUPSR SAMPLE INPUT 23
NEA1151_03.019 JENDL-3PR1 FOR SAMPLE PROBLEM 1396
NEA1151_03.020 PENDF FOR SAMPLE PROBLEM 1125
NEA1151_03.021 GENDF FOR SAMPLE PROBLEM 787
NEA1151_03.022 SEADR SAMPLE INPUT 11
NEA1151_03.023 COVFIL FOR SAMPLE PROBLEM 3103
NEA1151_03.024 SUSD SAMPLE INPUT 37
NEA1151_03.025 GROUPSR SAMPLE CASE OUTPUT, PRODUCED ON IBM 653
NEA1151_03.026 SEADR SAMPLE CASE OUTPUT, PRODUCED ON IBM 514
NEA1151_03.027 SUSD SAMPLE CASE OUTPUT, PRODUCED ON IBM 504
NEA1151_03.028 SUSD MODULE FOR TWODANT (FORTRAN) 507
NEA1151_03.029 SUSD MODULE FOR PN SENSITIVITY ANAL. 420
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • O. Experimental Data Processing

Keywords: angular distribution, covariance matrices, data uncertainties, neutron transport theory, radiation detectors, response functions, sensitivity analysis.