Benchmarking MCNP and TRIPOLI with PGNAA measurements
1 CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 St Paul-lez-Durance, France
2 FZJ, Institut für Energie-und Klimaforschung Nukleare Entsorgung und Reaktorsicherheit, Wilhelm-Johnen-Straße, DE-52428 Jülich, Germany
3 RWTH Aachen University, Institute of Nuclear Fuel Cycle, Elisabethstraße 16, D-52062 Aachen, Germany
* Corresponding Author, E-mail: firstname.lastname@example.org
The French Alternative Energies and Atomic Energy Commission (CEA Cadarache), the Forschungszentrum Jülich GmbH (FZJ), and the RWTH Aachen University (RWTH) are involved in a cooperation aiming at characterizing toxic and reactive elements in radioactive waste packages by means of Prompt Gamma Neutron Activation Analysis (PGNAA). The design of an optimized measurement system and the assessment of its performances for realistic scenarios can be conveniently studied by numerical Monte Carlo simulation, provided the model and nuclear data offer a sufficient precision.
Previous studies performed with MCNP have shown that when the nuclear data libraries lack of precision, relevant results can still be obtained by performing calculations in multiple steps (by first determining the radiative capture rate, and transporting the induced gamma toward the detector) and by injecting valid gamma-ray production data in-between . In such cases, it is interesting to compare the results obtained with different codes. In the present paper, we propose to compare the MCNP and TRIPOLI codes with measurements obtained in MEDINA (Multi Element Detection based on Instrumental Neutron Activation), which is the new FZJ PGNAA facility . The aim of the measurement campaign is to assess capture gamma rays of toxic elements that can be found in 200 L waste drums which are expected for geological repository.
© Owned by the authors, published by EDP Sciences, 2014