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CCC-0442 ACDOS3.

ACDOS3, Neutron Activation Activities and Dose Rates

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1. NAME OR DESIGNATION OF PROGRAM

ACDOS3

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2. COMPUTERS
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Program name Package id Status Status date
ACDOS3 CCC-0442/01 Tested 18-JAN-1985
ACDOS3 CCC-0442/02 Tested 07-MAR-1989

Machines used:

Package ID Orig. computer Test computer
CCC-0442/01 CDC 7600 DEC VAX 11/780
CCC-0442/02 CDC 7600 CDC CYBER 830
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3. DESCRIPTION OF PROGRAM OR FUNCTION

ACDOS3 is designed to calculate the activities and dose rates produced by neutron activation in a variety of simple geometries. Neutron fluxes, in up to 50 groups and with energies up to 20 MeV, must bes supplied as part of the input data. The neutron-source strength must also be supplied, or alternatively, the code will compute it from neutral- beam operating parameters in the case where the source is a fusion-reactor injector.

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4. METHODS

ACDOS3 first uses the group flux to calculate radioactive products and radioactive daughters of radioactive products, which are produced by single- or multiple-pulse neutron irradiation. Irradiated materials may take the form of solid or hollow spheres and cylinders or cylindrical shells. ACDOS3 next calculates the dose rate at an exterior point except in the case of a hollow sphere where an interior point may also be selected. The latter choice simulates the dose rate due to activation of a shielding cell. An option provides for a choise of self-absorption or no self-absorption of gammay rays in the materials irradiated. ACDOS3 also provides an option to compute the energy absorption in the irradiated materials due to the neutron reaction products.

 

The chief approximations used in ACDOS3 are that the gamma-ray dose rate is computed on the basis of analytical formulae. The latter often involve approximations and sometimes contain functions which have to be further approximated. This is particularly true for the coefficients used in buildup factors. In calculating the energy absorption in irradiated materials, ACDOS3 assumes that charge- particle reaction products are entirely absorbed and that gamma-ray reaction products can be treated by an average-chord method.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

None noted.

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6. TYPICAL RUNNING TIME

Running time for the ACDOS3 sample problem was 9.45 seconds from the compiled source.

CCC-0442/01
NEA-DB executed the test case included in the package on VAX-11/780 in 21 CPU seconds.

CCC-0442/02
The test case ran at NEA-DB on a CDC CYBER 830 computer in 13.7 seconds of CPU time.
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8. RELATED OR AUXILIARY PROGRAMS

ACDOS3 is an improved version of the neutron dose rate code ACDOS2, which was based on ACDOS1.

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9. STATUS
Package ID Status date Status
CCC-0442/01 18-JAN-1985 Tested at NEADB
CCC-0442/02 07-MAR-1989 Tested at NEADB
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10. REFERENCES
  • G.S. Keney:
    Dose Rates from Neutron Activation of Neutral-Beam Injectors, LBL-12244

  • M.S. Singh:
    D + D Reaction Neutron Yields from the Implantation of incident D+ in Metals, UCRL-77067, July 1975

  • M.A. Gardner and R.J. Howerton:
    ACTL Evaluation Neutron Activation Library, UCRL-50400, Vol. 18, October 1978

  • R.J. Howerton:
    Flux Weighted Group Cross Sections based on the ACTMLFE Data File  UCID-18749, July 1980

  • R.J. Howerton:
    ENSL, The LLNL Evaluated Nuclear Structure Library, UCRL-50400, Vol. 24

CCC-0442/01, included references:
- Catherine S. Martin:
  ACDOS3 - A Further Improved Neutron Dose Rate Code (M.S. Thesis).
  LBL-14547  (July 1982)
- Jean-Charles Lagache:
  ACDOS2 - An Improved Neutron-Induced Dose Rate Code (M.S. Thesis).
  LBL-12711  (June 1981)
CCC-0442/02, included references:
- Catherine S. Martin:
  ACDOS3 - A Further Improved Neutron Dose Rate Code (M.S. Thesis).
  LBL-14547  (July 1982)
- Jean-Charles Lagache:
  ACDOS2 - An Improved Neutron-Induced Dose Rate Code (M.S. Thesis).
  LBL-12711  (June 1981)
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11. HARDWARE REQUIREMENTS

Main storage requirements for the sample problem were approximately 61400 octal words to load and 47000 octal words to execute.

CCC-0442/01
74,240 bytes of main storage on VAX-11/780.

CCC-0442/02
The test case ran on a CDC CYBER 830 in 65,000 (octal)  words of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0442/01 FORTRAN-IV
CCC-0442/02 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS
CCC-0442/01
VMS V3.4 (VAX-11/780).

CCC-0442/02
NOS2.5.1 (CDC CYBER 830).
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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:    Lawrence Berkeley Laboratory, Berkeley, California, USA

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16. MATERIAL AVAILABLE
CCC-0442/01
File name File description Records
CCC0442_01.003 ACDOS3 INFORMATION FILE 51
CCC0442_01.004 ACDOS3 SOURCE PROGRAM (FORTRAN) 2084
CCC0442_01.005 ACTLMFE ACTIVATION LIBRARY (FORMATTED) 20654
CCC0442_01.006 LEVDEC DECAY LIBRARY (FORMATTED) 12962
CCC0442_01.007 DONNEE TEST CASE INPUT DATA 16
CCC0442_01.008 FLUXIN TEST CASE FLUX INPUT 5
CCC0442_01.009 ACDOS3 TEST CASE OUTPUT 283
CCC-0442/02
File name File description Records
CCC0442_02.001 Information file 45
CCC0442_02.002 JCL and control information 13
CCC0442_02.003 ACDOS3 source program 2077
CCC0442_02.004 ACTLMFE Eval. Neutron Activation Library 20654
CCC0442_02.005 LEVDEC Subset of LLNL nuclide decay libr. 12962
CCC0442_02.006 Sample problem input for Copper target 16
CCC0442_02.007 FLUXING sample problem input 5
CCC0442_02.008 Orig. output sample problem sent by the aut. 296
CCC0442_02.009 Output sample problem produced at NEA-DB 295
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: activation, dose rates, fusion reactors, gamma radiation, multigroup.