1. Numerical analysis of the alanine response using Monte Carlo: Correlation with experimental results
- Author
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W. Dridi, F. Rouihem, M. Daoudi, Patrick Blaise, Faouzi Hosni, G. Bignan, and K. Farah
- Subjects
Radiation ,Materials science ,Dosimeter ,Monte Carlo method ,Radiochemistry ,technology, industry, and agriculture ,Context (language use) ,Nuclear reactor ,law.invention ,law ,Absorbed dose ,Dosimetry ,Neutron ,Research reactor - Abstract
International centers based on research reactors (ICERR) project supported by IAEA, offers training and research in the application of advanced nuclear reactor technology. In this context of the project, alanine dosimeters were irradiated under mixed neutron/gamma irradiation in the core of the MINERVE research reactor at the CEA Cadarache. The integrated dose of the alanine was measured by electron spin resonance spectrometry with reference to an absorbed dose in water from a 60Co gamma-ray beam. Neutron and gamma dose components were calculated using the MCNP code. The neutron dose and relative effectiveness ( R E n ) for neutrons was evaluated using FLUKA code and Track Structure Theory (TST) formulations of alanine response towards irradiations with ions produced by neutron interactions with alanine. R E n values were found to be between 0.516 and 0.538. The measured dose was compared to the calculation results. The best agreement between the alanine integral measurements and model predictions (0.4%) was obtained by using the Cucinotta alanine detector response model.
- Published
- 2022
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