Large Sample Neutron Activation Analysis: correction for neutron and gamma attenuation

• Autorzy: Tzika F. , Stamatelatos I. , Kalef-Ezra J. , Bode P.
• Języki publikacji: EN

Abstrakty

EN

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.

Słowa kluczowe

EN

neutron activation analysis; neutron self-shielding; gamma-ray attenuation; MCNP code

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2004
• Tom: Vol. 49, nr 3
• Strony: 115--121
• Opis fizyczny: Bibliogr. 16 poz., rys.

Twórcy

autor

Tzika F.

• 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.: [phone], Fax: [phone]

autor

Stamatelatos I.

• Institute of Nuclear Technology and Radiation Protection, NCSR “Demokritos”, 15310 Aghia Paraskevi Attikis, Greece

autor

Kalef-Ezra J.

• Medical Physics Laboratory, Medical School, University of Ioannina, 45110 Ioannina, Greece

autor

Bode P.

• Interfaculty Research Institute, Delft University of Technology, 15 Mekelweg, 2629 JB Delft, The Netherlands

Bibliografia

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• 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
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• 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