Determination of neutron flux parameters (f, α, φth and φe) of the irradiation sites of Isfahan MNSR reactor using empirical and MCNPX2.6 simulation approaches-Reference-Cited by-同舟云学术

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Determination of neutron flux parameters (f, α, φth and φe) of the irradiation sites of Isfahan MNSR reactor using empirical and MCNPX2.6 simulation approaches

Published:2019-06 Issue: Volume:148 Page:80-86
ISSN:0969-8043
Container-title:Applied Radiation and Isotopes
language:en
Short-container-title:Applied Radiation and Isotopes

Author:

Soleimani B.,Rezvanifard M.,Ahmadi M.

Funder

Research Center of Isfahan MNSR Reactor

Publisher

Elsevier BV

Subject

Radiation

Reference34 articles.

1. Characterization of the Dalhousie University SLOWPOKE-2 reactor for k0-NAA and application to medium-lived nuclides;Acharya;J. Radioanal. Nucl. Chem.,2003

2. Characterization of neutron flux spectra in irradiation sites of MNSR reactor using the Westcott-formalism for the k0 neutron activation analysis method;Akaho;Appl. Radiat. Isot.,2002

3. Neutron Physics (L. Dresner, Trans.);Beckurts,1964

4. The k_0-Standardization Method: a Move to the Optimization of Neutron Activation Analysis;De Corte,1987

5. Recent advances in the k0-standardization of neutron activation analysis: extensions, applications, prospects;De Corte;J. Radioanal. Nucl. Chem.,1993

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