The International Atomic Energy Agency (IAEA) is implementing a Neutron Science Facility
(NSF) based on the use of deuterium-deuterium (DD) and deuterium-tritium (DT) neutron
generators to expand its domains of application and its training capabilities using neutrons
and associated techniques. Targeted applications include neutron radiography, neutron
activation analysis and production of radiotracers for training purposes.
This study presents the optimization of the design and the preliminary characterization of the
irradiation housing and shielding of a DT generator with a neutron yields of up to 4x108 n/s.
The irradiation housing increases the effectiveness of the neutron irradiation and contributes
to the shielding.
The optimization of housing and shielding has been performed using three types of Monte
Carlo Codes, namely Monte Carlo N-Particle (MCNP6.2), MCS Monte Carlo neutron/photon
transport code 0.1.6, and Monte Carlo Code for Advanced Reactor Design and analysis
Factors that drove the optimization were safety, performance, cost, mass, and commercial
availability of materials, as the final design is expected to serve as a good practice for IAEA
Member States implementing a similar facility.
Results related to the neutron spectrum and flux in the irradiation chamber of the housing as
well as neutron and dose rates outside of the shielding and in the facility will be presented.
Radiation dose rates are further decreased by the shielding, surrounding the irradiation
housing. The paper will include intercomparing the calculations performed with the three
codes and preliminary experimental measurements assessing the accuracy of the
Acknowledgements: The authors thank Valentin Blideanu who has provided, under a consultancy
contract with the IAEA, a valuable contribution to the very first modelling on shielding configurations.