PSR-0173: BON, Unfolding of Multisphere Spectrometer Neutron Spectra

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PSR-0173 BON. (Abstract last modified 16-AUG-1984)

BON, Unfolding of Multisphere Spectrometer Neutron Spectra

Abstract Table of Contents:

1. NAME OR DESIGNATION OF PROGRAM - BON.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status BON PSR-0173/01 Tested

Machines used: Package-ID Orig.Computer Test Computer PSR-0173/01 IBM 360 series IBM 3081

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).

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).

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME -

PSR-0173/01:

NEA-DB executed the test case on IBM 3081 in 0.6 sec.

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.

8. RELATED AND AUXILIARY PROGRAMS -

9. STATUS
PSR-0173/01: 16-AUG-1984 Tested at NEADB

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:
- R.S. Sanna:
  A Manual for BON: A Code for Unfolding Multisphere Spectrometer
  Neutron Measurements
  EMIL-394 (August 1981).

11. MACHINE REQUIREMENTS -

PSR-0173/01:

38K bytes of main storage on IBM 3081.

12. PROGRAMMING LANGUAGE(S) USED -
PSR-0173/01: FORTRAN-IV

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -

PSR-0173/01:

MVS-SP (IBM 3081).

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.

15. NAME AND ESTABLISHMENT OF AUTHOR -
Contributed by: Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.

16. MATERIAL AVAILABLE -
PSR-0173/01:
PSR0173_01.003    BON INFORMATION FILE                               45 records
PSR0173_01.004    BON SOURCE PROGRAM (FORTRAN-4)                    163 records
PSR0173_01.005    BON JCL FOR TEST CASE                              52 records
PSR0173_01.006    4X4 MM LI6 RESPONSE MATRIX (UNIT 1)                42 records
PSR0173_01.007    12.7X12.7 MM LI6 RESPONSE MATRIX                   33 records
PSR0173_01.008    TEST CASE PRINTED OUTPUT (UNIT 3)                  49 records

17. CATEGORIES -

- O. Experimental Data Processing

Keywords: DATA ANALYSIS, NEUTRON DETECTORS, NEUTRON FLUX, NEUTRON SPECTRA, SCINTILLATION DETECTORS, SPECTRA UNFOLDING, SPECTROMETERS