last modified: 17-NOV-1983 | catalog | categories | new | search |

CCC-0351 FALSTF.

FALSTF, Neutron Flux and Gamma Flux Detector Response Outside Cylindrical Shields

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1. NAME OR DESIGNATION OF PROGRAM:  FALSTF.
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2. COMPUTERS
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Program name Package id Status Status date
FALSTF CCC-0351/01 Tested 16-NOV-1983

Machines used:

Package ID Orig. computer Test computer
CCC-0351/01 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION

FALSTF is a multigroup kernel-  integration code which uses response functions to calculate activities for detectors located at points external to a shielding configuration.
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4. METHOD OF SOLUTION

FALSTF makes calculations using as input either an emergent particle density or fluxes calculated by the discrete ordinates transport (DOT) code for two-dimensional cylindrical geometry. Doses can be calculated for one or more detectors.
FALSTAF calculates response contributions from (user-determined) regions within the configuration and sums over the regions to obtain the total response. Both the last flight contribution by region and total response are output by the code. FALSTF will permit the input of a top boundary source and will include the source contribution in the total calculation.
The code can include the effects of a collimator or of a partially-shadowed detector.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

No study has been made by RSIC of typical running times for FALSTF.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0351/01 16-NOV-1983 Tested at NEADB
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10. REFERENCES:
CCC-0351/01, included references:
- Van Baker and R.L. Childs:
  FALSTF: Informal Notes.  (1979)
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11. MACHINE REQUIREMENTS

FALSTF is operable on either the IBM 360 or IBM 370 series of computers or the CDC computers.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0351/01 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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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.
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16. MATERIAL AVAILABLE
CCC-0351/01
File name File description Records
CCC0351_01.001 FALSTF INFORMATION FILE 76
CCC0351_01.002 DOT-3.5 SOURCE PROGRAM (FORTRAN-4) 5990
CCC0351_01.003 DOT-3.5 INPUT DATA (FT05F001) 45
CCC0351_01.004 DOT-3.5 BINARY OUTPUT (FT20F001) 24
CCC0351_01.005 DOT-3.5 JCL 64
CCC0351_01.006 FALSTF SOURCE PROGRAM (FORTRAN-4) 1976
CCC0351_01.007 AUXILIARY BSAM ROUTINES (ASSEMBLER) 421
CCC0351_01.008 ICLOCK SOURCE (ASSEMBLER) 90
CCC0351_01.009 FALSTF INPUT DATA (FT05F001) 40
CCC0351_01.010 FALSTF PRINTED OUTPUT (FT06F001) 259
CCC0351_01.011 FALSTF JCL 40
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: cylindrical, gamma detectors, kernels, multigroup, neutron detectors, neutrons, response functions, shielding, two-dimensional.