Neutron activation analysis - A nuclear technique used in the study and monitoring of environment
Creators
- 1. Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (Romania)
Description
The neutron activation analysis (NAA) was used at INR Pitesti since 1987 first for investigating the content (in Rb, Ba, La, Ce. Nd, Sm, Eu, Tb, Yb, Lu, Hf, Ta, Th, U, etc) of geological sample and, later on, for different toxic elements (like Al, V, Mn, As, Br, I, Cl, Fe, Sb, K, Na) in environmental samples (urban dust, ashes from coal burning), moss and lichen and other biological tissues. Adequate standards were prepared for high accuracy quantitative determinations. The following steps are done in NAA analyses: - collecting and preparation of samples; - reference standard preparation; - gamma spectrometry measurements; data processing. The principle of the method is explained. The concentration of the investigated element is determined from the intensity of the gamma rays from the neutron activated nuclei in comparison with gamma ray intensity from the standard sample of known concentration. The measurements are made by the TRIGA-14 MW Reactor provided with pneumatic system for sample circulation and gamma spectrometric measuring station. As a function of the sample's matrix composition and elements to be determined, established are: - the irradiation time; - irradiation location in the reactor and accordingly the neutron flux intensity. For instance, inside the beryllium reflector and thermal column the thermal neutron flux is 1013 n/cm2.s and 109 n/cm2.s, respectively. The gamma spectrometric system is composed of a PGT or ORTEC gamma radiation detector, ORTEC preamplifier, amplifier and stabilized high voltage supply, CT analog-to-digital converter, multichannel analyzer, IN 96 or P III computer and peripherals (printer, magnetic disk units). The energy resolution of the gamma spectrometric system is 1.8 keV for the 1332.5 keV line of 60 Co. For gamma spectra processing the GANAAS or GENIE-2000 codes supplied by IAEA (for P III) or dedicated codes supplied by INTERTECHNIQUE-France for IN-96 were used. A table is given presenting the detection limits as sensitivity values ranging from 10-12 g to 10-5 g for a number of elements
Availability note (English)
Available from author(s) or Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (RO). Fax 40-48-262449Additional details
Additional titles
- Original title (Romanian)
- Analiza prin activare - Tehnica nucleara utilizata in studiul si supravegherea mediului inconjurator
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Nuclear Power - Current Status and Perspectives. INR 1971-2001 Symposium. Volume II
- Imprint Pagination
- 304 p.
- Journal Page Range
- p. 299-300
Conference
- Title
- Nuclear Power - Current Status and Perspectives
- Original Conference Title
- Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum
- Acronym
- INR 1971-2001 Symposium
- Dates
- 13 Jul 2001
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 33001632
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DATA PROCESSING; ELEMENTS; G CODES; MULTI-ELEMENT ANALYSIS; NEUTRON ACTIVATION ANALYSIS; NEUTRON ACTIVATION ANALYZERS; PNEUMATIC TRANSPORT; RABBIT TUBES; SENSITIVITY; TRACE AMOUNTS; TRIGA TYPE REACTORS
- Descriptors DEC
- ACTIVATION ANALYSIS; CHEMICAL ANALYSIS; COMPUTER CODES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MEASURING INSTRUMENTS; PROCESSING; REACTION PRODUCT TRANSPORT SYSTEMS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TRANSPORT; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 fig., 1 tab. Imprint:Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum