IAEA1411 NAAPRO.
NAAPRO, Neutron Activation Analysis Prognosis and Optimization code
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNING TIME, UNUSUAL FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| NAAPRO | IAEA1411/03 | Tested | 08-AUG-2004 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA1411/03 | PC Windows |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
The code predicts the results and main characteristics (detection limits, determination limits, measurement limits and relative precision of the analysis) of neutron activation analysis (instrumental and radiochemical). Gamma-ray dose rates for different points of time after sample irradiation and input count rate of the spectrometry system are also predicted. The code uses standard Windows user interface and extensive graphical tools for the visualization of the spectrometer characteristics (efficiency, response and background) and simulated spectrum. Optimization part is not included in the current version of the code.
The code predicts the results and main characteristics (detection limits, determination limits, measurement limits and relative precision of the analysis) of neutron activation analysis (instrumental and radiochemical). Gamma-ray dose rates for different points of time after sample irradiation and input count rate of the spectrometry system are also predicted. The code uses standard Windows user interface and extensive graphical tools for the visualization of the spectrometer characteristics (efficiency, response and background) and simulated spectrum. Optimization part is not included in the current version of the code.
IAEA1411/03
This version corrects some minor bugs of version 02.[ top ]
4. METHODS
The code simulates gamma-ray spectrum of activation products for the specified analysis conditions. These are analysis time mode, analyzed sample mass and elemental composition, characteristics of irradiating neutron flux and irradiation conditions, gamma-spectrometry measurement geometry and background conditions, as well as detector and spectrometry system parameters. During calculation of gamma-ray yields of activation products the burnup and buildup of both radioactive and stable isotopes are taken into account.
The code simulates gamma-ray spectrum of activation products for the specified analysis conditions. These are analysis time mode, analyzed sample mass and elemental composition, characteristics of irradiating neutron flux and irradiation conditions, gamma-spectrometry measurement geometry and background conditions, as well as detector and spectrometry system parameters. During calculation of gamma-ray yields of activation products the burnup and buildup of both radioactive and stable isotopes are taken into account.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
Neutron self-shielding and gamma-ray self-absorption effects are neglected. Epithermal activation is calculated using infinite dilution resonance integrals with minimum energy 0.1 eV and 0.55 eV for irradiation without and with Cd shielding respectively. It is assumed that radiochemical separation is carried out just after the sample irradiation and it takes negligible time. The detector response is simulated assuming point source at the detector axis, neglecting by pile-up and true-coincidence summing effects, using zero-dead-time approximation and simplified backscatter-peak model.
Neutron self-shielding and gamma-ray self-absorption effects are neglected. Epithermal activation is calculated using infinite dilution resonance integrals with minimum energy 0.1 eV and 0.55 eV for irradiation without and with Cd shielding respectively. It is assumed that radiochemical separation is carried out just after the sample irradiation and it takes negligible time. The detector response is simulated assuming point source at the detector axis, neglecting by pile-up and true-coincidence summing effects, using zero-dead-time approximation and simplified backscatter-peak model.
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8. RELATED OR AUXILIARY PROGRAMS
MCNP code was used for generating detector responses. PREPRO-2000 and FCONV programs were used at the preparation of the program nuclear databases. A special program was developed for viewing, editing and updating of the program databases (not included into the present program package).
MCNP code was used for generating detector responses. PREPRO-2000 and FCONV programs were used at the preparation of the program nuclear databases. A special program was developed for viewing, editing and updating of the program databases (not included into the present program package).
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10. REFERENCES
- V.K.Basenko, A.N.Berlizov, I.A.Malyuk, V.V.Tryshyn:
NAAPRO: A Code for Predicting Results and Performance of Neutron Activation Analysis, The Sixth International Conference on Methods and Applications of Radioanalytical Chemistry - MARC VI, Kailua-Kona, Hawaii, USA, April 7-11, 2003, Book of Abstracts, p.71; to be published in Jour. Rad. Nucl. Chem.
- V.K.Basenko, A.N.Berlizov, I.A.Malyuk, V.V.Tryshyn:
NAAPRO: A Code for Predicting Results and Performance of Neutron Activation Analysis, The Sixth International Conference on Methods and Applications of Radioanalytical Chemistry - MARC VI, Kailua-Kona, Hawaii, USA, April 7-11, 2003, Book of Abstracts, p.71; to be published in Jour. Rad. Nucl. Chem.
IAEA1411/03, included references:
- V.K.Basenko, A.N.Berlizov, R.H.Filby, I.A.Malyuk, V.V.Tryshyn:NAAPRO (Neutron Activation Analysis PRognosis and Optimization) Version 01.beta
User's Guide
- V.K.Basenko, A.N.Berlizov, R.H.Filby, I.A.Malyuk, V.V.Tryshyn:
NAAPRO (Neutron Activation Analysis PRognosis and Optimization) Version 01.beta
Model Description
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15. NAME AND ESTABLISHMENT OF AUTHORS
This code was developed in the Institute for Nuclear Research of the National Academy of Sciences of Ukraine in collaboration with Washington State University under the project #Uzb-26(J), sponsored by the United States Government through the Science and Technology Center in Ukraine.
Dr. Andriy Berlizov, Dr. Vladyslav Basenko
Institute for Nuclear Research
National Academy of Sciences of Ukraine
47 Prospekt Nauki, MSP 03680
Kyiv, UKRAINE
Prof. Royston H. Filby,
Washington State University
Department of Chemistry
P.O.Box 644630, Pullman, WA, USA
This code was developed in the Institute for Nuclear Research of the National Academy of Sciences of Ukraine in collaboration with Washington State University under the project #Uzb-26(J), sponsored by the United States Government through the Science and Technology Center in Ukraine.
Dr. Andriy Berlizov, Dr. Vladyslav Basenko
Institute for Nuclear Research
National Academy of Sciences of Ukraine
47 Prospekt Nauki, MSP 03680
Kyiv, UKRAINE
Prof. Royston H. Filby,
Washington State University
Department of Chemistry
P.O.Box 644630, Pullman, WA, USA
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IAEA1411/03
NAA.AVI Animation fileNAAPRO.exe Executable
NAAPRO-V01b_Model_Description.pdf Documentation
NAAPRO-V01b_User_Guide.pdf Documentation
binary Libraries
Tests input files
Tests output files
Keywords: activation analysis, gamma ray, neutron.