PSR-0233 LSL-M2.

LSL-M2, Neutron Spectra Log Adjustment for Dosimetry Applications

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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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.