Large-sample neutron activation analysis: Present status and prospects
- 120 Downloads
Neutron activation analysis is attractive for trace-element determinations in large samples. Facilities for reactor irradiation and γ-ray spectrometry of kilogram-size cylindrical samples are described. The thermal neutron flux is ca. 5·1012m−2·s−1 with aΦth/Φepi>104, so neutron self-thermalization can be neglected. The correction for the neutron attenuation within the sample is derived from measurement of the neutron flux depression just outside the sample. Correction for γ-attenuation in the sample is performed via linear attenuation coefficients derived via transmission measurements. Also the natural radioactivity in the sample is taken into account. Examples are given of materials to which large sample INAA has been applied successfully, and further lines of development and exploration are indicated.
KeywordsNeutron Activation Analysis INAA Attenuation Coefficient Neutron Flux Thermal Neutron
Unable to display preview. Download preview PDF.
- 2.A. J. J. Bos, J. E. Hoogenboom, Calculations and measurements of neutron fields in a facility for big sample neutron activation analysis at the research reactor at Delft, Proc. 1996 Radiation Protection & Shielding Topical Meeting on Advances and Applications in Radiation Protection and Shielding, No. Falmouth, Mass., USA, April 21–25, 1996.Google Scholar
- 3.W. A. Rhoades, R. L. Childs, Nucl. Sci. Eng., 107 (1991) 397.Google Scholar
- 4.P. Bode, J. Trace Microprob. Techn., 8 (1990) 139.Google Scholar
- 5.R. M. W. Overwater, P. Bode, J. J. M. de Goeij, Nucl. Instr. Meth., A 324 (1993) 209.Google Scholar
- 6.R. M. W. Overwater, J. E. Hoogenboom, Nucl. Sci. Eng., 116 (1994) 141.Google Scholar
- 8.O. Lakmaker, M. Blaauw, J. Radioanal. Nucl. Chem., to be published.Google Scholar