CCC-0442 ACDOS3.
ACDOS3, Neutron Activation Activities and Dose Rates
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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| 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.
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. METHOD OF SOLUTION
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.
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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6. TYPICAL RUNNING TIME
Running time for the ACDOS3 sample problem was 9.45 seconds from the compiled source.
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.[ top ]
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| 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
- 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. MACHINE REQUIREMENTS
Main storage requirements for the sample problem were approximately 61400 octal words to load and 47000 octal words to execute.
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.[ top ]
| Package ID | Computer language |
|---|---|
| CCC-0442/01 | FORTRAN-IV |
| CCC-0442/02 | FORTRAN-IV |
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CCC-0442/01
VMS V3.4 (VAX-11/780).CCC-0442/02
NOS2.5.1 (CDC CYBER 830).[ top ]
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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 |
Keywords: activation, dose rates, fusion reactors, gamma radiation, multigroup.