NAAPRO, Neutron Activation Analysis Prognosis and Optimization code
Creators
- 1. Institute for Nuclear Research, National Academy of Sciences of Ukraine, 47 Prospekt Nauki, MSP 03680, Kyiv (Ukraine)
- 2. Washington State University, Department of Chemistry, P.O. Box 644630, Pullman, WA (United States)
Description
A - 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. IAEA1411/03: Description: This version corrects some minor bugs of version 02. B - 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. C - 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 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 no. Uzb-26(J), sponsored by the United States Government through the Science and Technology Center in Ukraine.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39107383
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Computer Program Description, Non-conventional Literature
- Descriptors DEI
- APPROXIMATIONS; BURNUP; COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; COUNTING RATES; DEAD TIME; DOSE RATES; GAMMA RADIATION; GAMMA SPECTRA; GAMMA SPECTROSCOPY; GEOMETRY; IRRADIATION; N CODES; NEUTRON ACTIVATION ANALYSIS; NEUTRON FLUX; OPTIMIZATION; POINT SOURCES; RADIOCHEMISTRY; RESONANCE INTEGRALS; SELF-ABSORPTION; SELF-SHIELDING; SENSITIVITY; STABLE ISOTOPES; WEBSITES
- Descriptors DEC
- ABSORPTION; ACTIVATION ANALYSIS; CALCULATION METHODS; CHEMICAL ANALYSIS; CHEMISTRY; COMPUTER CODES; DOCUMENT TYPES; ELECTROMAGNETIC RADIATION; INTEGRALS; IONIZING RADIATIONS; ISOTOPES; MATHEMATICS; NONDESTRUCTIVE ANALYSIS; RADIATION FLUX; RADIATION SOURCES; RADIATIONS; SIMULATION; SORPTION; SPECTRA; SPECTROSCOPY; TIMING PROPERTIES
Optional Information
- Notes
- 3 refs.