NEA-1343 ANITA.
ANITA-4, Isotope Inventories from Neutron Irradiation, for Fusion Applications
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 |
|---|---|---|---|
| ANITA-4 | NEA-1343/03 | Tested | 09-JUL-1998 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1343/03 | IBM 370 series | PC Pentium 200,RISC 6000 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
The code computes the radioactive inventory of a material subject to neutron irradiation, continuous or stepwise. It provides activity, atomic density, decay heat, energy of decay gamma-rays and ingestion hazard of each nuclide; total activity, decay heat, contact dose equivalent, gamma-ray spectra, and other relevant parameters, for the irradiated material, versus cooling time. As an option, these parameters may be plotted as a function of the cooling time.
The code is provided with a complete data base allowing to perform calculations for all the elements with atomic number smaller than 84 (up to bismuth). The cross-sections and the decay data library have been developed in view of the application to fusion technology.
The code computes the radioactive inventory of a material subject to neutron irradiation, continuous or stepwise. It provides activity, atomic density, decay heat, energy of decay gamma-rays and ingestion hazard of each nuclide; total activity, decay heat, contact dose equivalent, gamma-ray spectra, and other relevant parameters, for the irradiated material, versus cooling time. As an option, these parameters may be plotted as a function of the cooling time.
The code is provided with a complete data base allowing to perform calculations for all the elements with atomic number smaller than 84 (up to bismuth). The cross-sections and the decay data library have been developed in view of the application to fusion technology.
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NEA-1343/03
The test case included in the package was executed by the NEA Data Bank on a PC/200MHz in 3.4sec; and on a IBM RISC/6000 workstation in 2.5sec.[ top ]
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8. RELATED AND AUXILIARY PROGRAMS
NUCLIST - prints the content of the decay data library
DISCHO - may be used to provide graphical display of the results of ANITA
NEODIR - reads the activation cross section library in EBCDIC form and build a Direct Access Library for ANITA
NEOLIST - prints the content of Direct Access cross section library
ZZ-GEAF-1 - 100 groups European Activation File
NUCLIST - prints the content of the decay data library
DISCHO - may be used to provide graphical display of the results of ANITA
NEODIR - reads the activation cross section library in EBCDIC form and build a Direct Access Library for ANITA
NEOLIST - prints the content of Direct Access cross section library
ZZ-GEAF-1 - 100 groups European Activation File
NEA-1343/03
The following programs are included with the package: MODBIN (formerly NEODIR) builds a direct access binary library from a card image activation file; GRANITA (formerly DISCHO) produces graphical output (in encapsulated PostScritpt format) from the inventory file generated by ANITA-4.[ top ]
10. REFERENCES
- C. Ponti:
Calculation of Radioactive Decay Chains Produced by Neutron
Irradiation
EUR 9389 (1984).
- C. Ponti:
Validation of Activation Inventory Codes
Paper presented at the Techn. Committee on Selected Aspects of
Fusion Reactor Safety, Jackson, USA (1989).
- J. Kopecky and H.A.J. Van Der Kamp:
Evaluation of Cross-Sections and Uncertainties for Important
Reactions - A Supplement to REAC-ECN-5 Data File.
ECN-89-181.
- D. Cepraga et al.:
Activation of TZM and Stainless Steel Divertor Materials in the
NET Fusion Machine
Reprinted from Journal of Nuclear Materials 212-215 (94) 644-648
- D. Cepraga et al.:
Neutron Transport, Activation Calculations and Sensitivity
Analyses for ITER-EDA
(Safety & Environment Meeting, October 10-14, 1994)
- C. Ponti:
Calculation of Radioactive Decay Chains Produced by Neutron
Irradiation
EUR 9389 (1984).
- C. Ponti:
Validation of Activation Inventory Codes
Paper presented at the Techn. Committee on Selected Aspects of
Fusion Reactor Safety, Jackson, USA (1989).
- J. Kopecky and H.A.J. Van Der Kamp:
Evaluation of Cross-Sections and Uncertainties for Important
Reactions - A Supplement to REAC-ECN-5 Data File.
ECN-89-181.
- D. Cepraga et al.:
Activation of TZM and Stainless Steel Divertor Materials in the
NET Fusion Machine
Reprinted from Journal of Nuclear Materials 212-215 (94) 644-648
- D. Cepraga et al.:
Neutron Transport, Activation Calculations and Sensitivity
Analyses for ITER-EDA
(Safety & Environment Meeting, October 10-14, 1994)
NEA-1343/03, included references:
- C. Ponti and S. Stramaccia:ANITA - Analysis of Neutron Induced Transmutation and Activation
EUR 12622 (1989).
- D.G. Cepraga, G. Cambi, M. Frisoni and G.C. Panini:
ANITA-4: A Code for Material Irradiation Characterization in
Fusion Neutron Spectra
Draft Manual (June 1998)
- D.G. Cepraga, G. Cambi, M. Frisoni and F. Carloni:
Fusion-Related Materials Decay Heat Evaluatoin: A Comparison
with Experiments
Invited Paper
American Nuclear Society, 1998 Annual Meeting
13th Topical Meeting on the Technology of Fusion Energy
June 7-11, 1998 - Nashville TN (Preprint)
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11. MACHINE REQUIREMENTS
The program itself requires about 1250 Kbytes. With buffers, it has been running in a memory region of 1500 Kbytes. It uses nine I/O channels, including standard input (5) and standard output (6). On unit 3 a direct access file is allocated, so it must reside on a disc.
The program itself requires about 1250 Kbytes. With buffers, it has been running in a memory region of 1500 Kbytes. It uses nine I/O channels, including standard input (5) and standard output (6). On unit 3 a direct access file is allocated, so it must reside on a disc.
NEA-1343/03
The program has been installed by the NEA Data Bank on a PC with Intel Pentium 200MHz processor and on an IBM RISC/6000 Workstation.[ top ]
| Package ID | Computer language |
|---|---|
| NEA-1343/03 | FORTRAN-77, FORTRAN-90 |
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NEA-1343/03
The PC installation was done under MS-DOS (Windows 95) with Lahey f77 5.2 and f90 3.50a compilers. The IBM RISC/6000 installation was done under AIX 3.2 with the xlf compiler.[ top ]
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NEA-1343/03
MISTPMaterial for ANITAREPPTEUR12622 EN (1989) PREPRINT
REPPTDRAFT MANUAL (June 1998)
PAPPTAm.Nucl.Soc. 1998 Annual Meeting (June 98)
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- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
- X. Magnetic Fusion Research
Keywords: decay heat, fusion reactors, ingestion, inventories, irradiation, isotope production, radioactive decay.