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PSR-0233 LSL-M2.

LSL-M2, Neutron Spectra Log Adjustment for Dosimetry Applications

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1. NAME OR DESIGNATION OF PROGRAM:  Least-Squares Logarithmic
Adjustment of Neutron Spectra.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
LSL-M2 PSR-0233/01 Tested 24-JUL-1995

Machines used:

Package ID Orig. computer Test computer
PSR-0233/01 DEC VAX 6000 DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

LSL-M2 adjusts calculated neutron spectra to make the fluence values consistent with given neutron dosimetry measurements. The primary output is a set of values for the best estimates of damage parameter values; the solution is based on a least squares fit of all input data.
Several input spectra, possibly from different irradiations, can be  processed simultaneously.
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4. METHOD OF SOLUTION

In an adjustment procedure, consistency is achieved by adjusting the input data in such a manner that a weighted sum of squares of adjustments is minimized. The weights are assigned according to the input uncertainties, i.e., the larger the  uncertainty, the smaller the weight. This sum, which is further modified by correlations, represents the negative logarithm of the probability of the outcome of the experiment if the adjusted values  are the "true" data.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The results of the adjustment are valid only if the size of the adjustment does not exceed the input uncertainties. The user should also guard against adjustments that exceed the limitations given by the linearization of the problem.
The number of spectra times the number of energy groups may not exceed 400. The number of dosimetry measurements must not exceed 100.
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6. TYPICAL RUNNING TIME

To compile and link source codes and execute  8 sample problems on an IBM PC required about 2 hours. Compiling LSL-M2 required more than 30 minutes. The AT is, of course, much faster.
PSR-0233/01
To compile and link source codes and execute 8 sample problems on an IBM PC required about 2 hours. Compiling LSL-M2 required more than 30 minutes. The AT is, of course, much faster. - The following Table displays the CPU time necessary to run seven out of the eight the test cases on the VAX 6000-510 machine (running OpenVMS V6.1):
                   ------------------------------------
                   |                  |               |
                   |    Test Case #   |   CPU time    |
                   |     (filename)   |   (seconds)   |
                   ====================================
                   |  1 (RUNFLX1.COM) |     10.63     |
                   ------------------------------------
                   |  2 (RUNFLX2.COM) |      6.95     |
                   ------------------------------------
                   |  3 (RUNFLX3.COM) |      7.11     |
                   ------------------------------------
                   |  4 (RUNACT4.COM) |      4.55     |
                   ------------------------------------
                   |  5 (RUNFLX5.COM) |     17.27     |
                   ------------------------------------
                   |  7 (RUNACT7.COM) |      8.12     |
                   ------------------------------------
                   |  8 (RUNLSL8.COM) |     12.74     |
                   ====================================
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

AUXILIARY ROUTINES:
ACT:  Converts from dosimeter activities to reaction rates.
CALACT: Determines calculated reaction rates from fluences and cross sections.
FLXPRO: Converts fluences, cross sections, and covariances from one group structure to another.
DATA LIBRARIES:
CROSS.XSO: Dosimetry cross section file obtained from IRDF-8 as distributed with the REAL84 exercise.
DAMAGE.XSO: Contains dpa cross sections as given in AST Standard E693-79.
SPVC.XSO: Based on the determination of fluence covariances in the ORR-PSV experiment.
LSLNUC.DAT:  Obtained from the Nuclear Data Guide.
PSR-0233/01
ACT                 Dosimeter activity to reaction rate conversion
CALACT              Reaction rates from fluences and x-sections
FLXPRO              fluence,x-section,covariance group conversion
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9. STATUS
Package ID Status date Status
PSR-0233/01 24-JUL-1995 Tested at NEADB
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10. REFERENCES

- D.E. Cullen and P.K. McLaughlin, "The International Reactor
  Dosimetry File (IRDF-85)", (April 1985).
- W.L. Zijp, E.M. Zsolnay, and D.E. Cullen, "Information sheet for
  the REAL84 exercise", Report INDC(NDC)-166 (March 1, 1985).
- R.E. Maerker, J.J. Wagschal, and B.L. Broadhead, "Development and
  Demonstration of an Advanced Methodology for LWR Dosimetry
  Applications", EPRI-NP-2188 (1981).
- W.L. Zijp and J.H. Baard, "Nuclear Data Guide for Reactor Neutron
  Metrology, Part 1 and Part 2", ECN70/71 (1979).
PSR-0233/01, included references:
- F.W. Stallmann:
  LSL-M2 - A Computer Program for Least-Squares Logarithmic
  Adjustment of Neutron Spectra
  NUREG/CR-4349, ORNL/TM-9933 (March 1985).
- J.L. Bartley:
  Comments on Packaging PSR-233Micro/LSL-M2
  Informal Notes (September 1986).
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11. MACHINE REQUIREMENTS

LSL-M2 is operable on a IBM PC-AT or IBM with fixed disk, an 8087 match coprocessor and 640K memory. It also runs  on the VAX family of computers.
PSR-0233/01
The programs were installed by NEA-DB on a DEC VAX 6000/510 computer.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0233/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

IBM Personal Computer Professional Fortran, Version 1.0, is required. The VAX version runs under the VMS operating system, using the VAX FORTRAN compiler.
The code was run at RSIC under PC DOS 3.1. The VAX version was tested on a VAX 6000.
PSR-0233/01
- The source code files for the main program (LSLM2.FOR), and of the three auxiliary programs (ACT.FOR, CALACT.FOR and FLXPRO.FOR) were compiled with the DEC FORTRAN-77 compiler. The executables were run under OpenVMS V6.1.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Oak Ridge National Laboratory,
                Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
PSR-0233/01
File name File description Records
PSR0233_01.001 LSL-M2 Information File 408
PSR0233_01.002 Source file of main program LSL-M2 3723
PSR0233_01.003 Source file of auxiliary program ACT 1245
PSR0233_01.004 Source file of auxiliary program CALACT 308
PSR0233_01.005 Source file of auxiliary program FLXPRO 893
PSR0233_01.006 Command file to create the executables 9
PSR0233_01.007 Command file to run FLXPRO (test case #1) 20
PSR0233_01.008 Command file to run FLXPRO (test case #2) 16
PSR0233_01.009 Command file to run FLXPRO (test case #3) 16
PSR0233_01.010 Command file to run ACT (test case #4) 10
PSR0233_01.011 Command file to run FLXPRO (test case #5) 22
PSR0233_01.012 Command file to run CALACT (test case #6) 2
PSR0233_01.013 Command file to run ACT (test case #7) 20
PSR0233_01.014 Command file to run LSL-M2 (test case #8) 20
PSR0233_01.015 Master file to run LSL-M2 12
PSR0233_01.016 File with the reaction rates (FOR020.DAT) 46
PSR0233_01.017 Total fluence file (FOR022.DAT) 23
PSR0233_01.018 20-group averaged x-sections (FOR023.DAT) 26
PSR0233_01.019 Reaction rate covariances file (FOR024.DAT) 12
PSR0233_01.020 20-group fluence covariances (FOR025.DAT) 28
PSR0233_01.021 20-group x-sect. covariances (FOR026.DAT) 195
PSR0233_01.022 Alternative file to LSLM2.XSV 28
PSR0233_01.023 20-group damage x-sect. file (FOR027.DAT) 17
PSR0233_01.024 Adjusted fluence and reaction rates 214
PSR0233_01.025 Damage parameters before adjustment 44
PSR0233_01.026 Damage parameters after adjustment 46
PSR0233_01.027 Covariance matrix of residuals 71
PSR0233_01.028 C/E ratios and response intervals 112
PSR0233_01.029 Cross-sections and fluence covariance 172
PSR0233_01.030 Mirror output for reaction rates and fluence 69
PSR0233_01.031 Master file to run program ACT 9
PSR0233_01.032 Master file to obtain irradiation times 9
PSR0233_01.033 Irradiation history file 23
PSR0233_01.034 Activity file 40
PSR0233_01.035 Activity correction file 6
PSR0233_01.036 File with the calculated activities 52
PSR0233_01.037 Nuclear data file 64
PSR0233_01.038 Output direction file 14
PSR0233_01.039 Irradiation history (output file) 23
PSR0233_01.040 20-group fluences file 49
PSR0233_01.041 File to create the input to CALACT 57
PSR0233_01.042 Master file for cross-sections 29
PSR0233_01.043 Alternative file to CROSS.PRO 30
PSR0233_01.044 Master file for damage parameters 8
PSR0233_01.045 Converts fluence energy structures 40
PSR0233_01.046 Master file for fluence covariances 8
PSR0233_01.047 ENDF/B dosimetry cross-sections library file 2061
PSR0233_01.048 Damage cross-sections library file 116
PSR0233_01.049 Fluence covariances file from SPV experiment 177
PSR0233_01.050 Input energy groups 12
PSR0233_01.051 Input fluences 110
PSR0233_01.052 Reference energy groups file 107
PSR0233_01.053 Reference spectrum in 620 energy groups 65
PSR0233_01.054 Output energy groups file 5
PSR0233_01.055 Output energy groups file 10
PSR0233_01.056 Miscellaneous 7
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: least square fit, neutron spectra, nuclear damage.