last modified: 16-AUG-1984 | catalog | categories | new | search |

PSR-0173 BON.

BON, Unfolding of Multisphere Spectrometer Neutron Spectra

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1. NAME OR DESIGNATION OF PROGRAM:  BON.
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2. COMPUTERS
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Program name Package id Status Status date
BON PSR-0173/01 Tested 16-AUG-1984

Machines used:

Package ID Orig. computer Test computer
PSR-0173/01 IBM 360 series IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION

BON unfolds neutron spectra measured with a multisphere spectrometer consisting of thermal neu-  tron detectors, one exposed bare, one inside a cadmium shield, and one each at the center of polyethylene spheres of varying diameters  (7). Each of the counters has a different energy response to neu- trons.

BON yields a differential energy spectrum and, if the system is calibrated with a known source, the integral of the spectrum is the  total neutron fluence rate. Published flux-to-dose conversion fac- tors are folded into the spectrum to yield the absorbed dose and dose-equivalent rates (8) (9).
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4. METHOD OF SOLUTION

The homogeneous Fredholm equation is solved by  the iterative method of Scofield and Gold (1) (2). The technique has been adapted to the problem of unfolding neutron spectra from multi- sphere spectrometer data (3).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
PSR-0173/01
NEA-DB executed the test case on IBM 3081 in 0.6 sec.
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7. UNUSUAL FEATURES OF THE PROGRAM

The code has the capability of analyzing batches of measurements using different response matrices  (i.e. different detectors) in a single run.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
PSR-0173/01 16-AUG-1984 Tested at NEADB
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10. REFERENCES

- N.E. Scofield:
  A Technique for Unfolding Gamma-Ray Scintillation Spectrometer
  Pulse-Height Distributions
  U.S. Navy Report USNRDL-TR-447 (1960)
- R.E. Gold:
  Iterative Solution for the Matrix Representation of Detector
  Systems
  USAEC Report TID-18304 (1960)
- K. O'Brien, R. Sanna, J. McLaughlin:
  Inference of Accelerator Stray Neutron Spectra from Various
  Measurements, p. 286 in Accelerator Radiation Dosimetry and
  Experience
  USAEC Report CONF-651109 (1965)
- R. Sanna:
  Modification of an Iterative Code for Unfolding Neutron from
  Multisphere Data
  USERDA Report HASL-311 (1976)
- R. Sanna:
  Thirty-One Group Response Matrices for the Multisphere Neutron
  Spectrometer Over the Energy Range Thermal to 400 MeV
  USAEC Report HASL-267 (1973)
- R. Sanna, F. Hajnal, J. McLaughlin, J. Gulbin, R. Ryan:
  Neutron Measurements Inside PWR Containments
  USDOE Report EML-379 (1980)
- R.L. Bramblett, R.I. Ewing, T.W. Bonner:
  A New Type of Neutron Spectrometer
  Nucl. Instr. Meth. 9, 1 (1960)
- Protection Against Neutron Radiation
  National Council of Radiation Protection and Measurements
  Report NCRP-38 (1971)
- Neutron and Gamma-Ray Flux-to-Dose-Rate Factors
  American Nuclear Society Committee Working Group
  ANSI/ANS-6.1.1 - 1977 (1977)
- F.H. Attix, E. Tochlin (Editors)
  Radiation Dosimetry, Vol. III, p. 207
  Academic Press, New York (1969)
PSR-0173/01, included references:
- R.S. Sanna:
  A Manual for BON: A Code for Unfolding Multisphere Spectrometer
  Neutron Measurements
  EMIL-394 (August 1981).
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11. MACHINE REQUIREMENTS:
PSR-0173/01
38K bytes of main storage on IBM 3081.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0173/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
PSR-0173/01
MVS-SP (IBM 3081).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The distributed version of the program is for the IBM-360 computers. To run it on the CDC-6600. the "C" in column 1 of the first card must be removed.
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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:   Environmental Measurements Laboratory,
                U.S. Department of Energy, New York, New York, USA
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16. MATERIAL AVAILABLE
PSR-0173/01
File name File description Records
PSR0173_01.003 BON INFORMATION FILE 45
PSR0173_01.004 BON SOURCE PROGRAM (FORTRAN-4) 163
PSR0173_01.005 BON JCL FOR TEST CASE 52
PSR0173_01.006 4X4 MM LI6 RESPONSE MATRIX (UNIT 1) 42
PSR0173_01.007 12.7X12.7 MM LI6 RESPONSE MATRIX 33
PSR0173_01.008 TEST CASE PRINTED OUTPUT (UNIT 3) 49
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17. CATEGORIES
  • O. Experimental Data Processing

Keywords: data analysis, neutron detectors, neutron flux, neutron spectra, scintillation detectors, spectra unfolding, spectrometers.