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A Large Sample Neutron Activation Analysis (LSNAA) facility is under development at the GRR-1 research reactor, NCSR "Demokritos". The LSNAA facility design incorporates sample irradiation in the reactor graphite thermal neutron column and subsequent measurement of the activity induced in a gamma spectroscopy system with gamma ray transmission measurement options included. The Monte Carlo neutron and photon transport code MCNP-4C was used to model the facility. Appropriate correction factors accounting for neutron field perturbation during sample irradiation and high-purity germanium detector efficiency for the volume source were derived. The results of the computations were experimentally verified by measurements for a set of known materials. The LSNAA facility will be used to perform multi-element, non-destructive, contamination-free analysis of large volume samples with high sensitivity and excellent sampling. End-users of the facility will be archaeological, environmental, bio-medical research laboratories and industry.
Czasopismo
Rocznik
Tom
Strony
115--121
Opis fizyczny
Bibliogr. 16 poz., rys.
Twórcy
autor
- Institute of Nuclear Technology and Radiation Protection, NCSR “Demokritos”, 15310 Aghia Paraskevi Attikis, Greece
- Medical Physics Laboratory, Medical School, University of Ioannina, 45110 Ioannina, Greece, Tel.: +30 210 6503713, Fax: +30 210 6533431
autor
- Institute of Nuclear Technology and Radiation Protection, NCSR “Demokritos”, 15310 Aghia Paraskevi Attikis, Greece
autor
- Medical Physics Laboratory, Medical School, University of Ioannina, 45110 Ioannina, Greece
autor
- Interfaculty Research Institute, Delft University of Technology, 15 Mekelweg, 2629 JB Delft, The Netherlands
Bibliografia
- 1. Baas HW, Blaauw M, Bode P, De Goeij JJM (1999) Collimated scanning towards 3D-INAA of inhomogeneous large samples. Fresenius J Anal Chem 363:753−759
- 2. Blaauw M, Baas HW, Donze M (2003) Height-resolved largesample INAA of a 1 m long, 13 cm diameter ditch-bottom sample. Nucl Instrum Meth A 505:512−516
- 3. Bode P, Lakmaker O, Van Aller P, Blaauw M (1998) Feasibility studies of neutron activation analysis with kilogram-size samples. Fresenius J Anal Chem 360:10−17
- 4. Bode P, Overwater RMW (1993) Trace element determinations in very large samples: a new challenge for neutron activation analysis. J Radioanal Nucl Chem 167:169−176
- 5. Briesmeister JF (ed) (2000) MCNP − A General Monte Carlo N-Particle Transport Code, Version 4C. LA-13709-M. Los Alamos National Laboratory, Los Alamos, USA
- 6. Degenaar IH, Blaauw M, De Goeij JJM (2003) Correction for neutron self-shielding in large-sample prompt-gamma neutron activation analysis: determination of macroscopic neutron cross sections. J Radioanal Nucl Chem 257:467−470
- 7. Fleming RF (1982) Neutron self-shielding factors for simple geometries. Appl Radiat Isot 33:1263−1268
- 8. Hubbel JH, Seltzer SM (1995) Tables of X-ray mass attenuation coefficients and mass energy-absorption coefficients 1 keV to 20 MeV for elements Z=1 to 92 and 48 additional substances of dosimetric interest. NISTIR-5632
- 9. International Atomic Energy Agency (1970) Neutron fluence measurements. Technical Reports Series No 107. IAEA, Vienna
- 10. Meghreblian RV, Holmes DK (1960) Reactor analysis. McGraw-Hill Book Company Inc, New York
- 11. Overwater RMW, Bode P (1998) Computer simulations of the effects of inhomogeneities on the accuracy of large sample INAA. Appl Radiat Isot 8:967−976
- 12. Overwater RMW, Bode P, De Goeij JJM (1993) Gammaray spectroscopy of voluminous sources: corrections for source geometry and self-attenuation. Nucl Instrum Meth A 324:209−218
- 13. Overwater RMW, Bode P, De Goeij JJM, Hoogenboom JE (1996) Feasibility of elemental analysis of kilogram-size samples by instrumental neutron activation analysis. Anal Chem 68:341−348
- 14. Overwater RMW, Hoogenboom JE (1994) Accounting for the thermal neutron flux depression in voluminous samples for instrumental neutron activation analysis. Nucl Sci Eng 117:141−157
- 15. Shakir NS, Jervis RE (2001) Correction factors required for quantitative large volume INAA. J Radioanal Nucl Chem 248:61−68
- 16. Tzika F, Stamatelatos IE (2004) Thermal neutron selfshielding correction factors for large sample instrumental neutron activation analysis using the MCNP code. Nucl Instrum Meth B 213:177−181
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ6-0005-0057