Characterization of the gamma flux in a tangential channel of the CENM TRIGA MARK II research reactor

¹ CEA, DEN, Cadarache, DER/SPESI, F-13108 Saint Paul lez Durance, France
² DIN/CNESTEN, POB 1382, Rabat, Morocco

adrien.gruel@cea.fr

Published online: 31 January 2020

Abstract

The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA Mark II reactor, which can reach a thermal maximum power at steady state of 2 MW. In reactors devoted to research and experiments, it is mandatory to characterize the neutron and photon fields in the irradiation positions. Together with a computational model of the core, it ensures the ability to reach the requested uncertainties when performing experiments, such as detectors testing, irradiation for hardening or nuclear data measurements.

The neutron field of different irradiation positions has been characterized by dosimetry techniques and compared to the MCNP full model of the reactor. Preliminary photon propagation calculations are also performed with this model, but up to now, no experimental validation of the results exists. The aim of the newly set collaboration between CEA and CNESTEN is to characterize the gamma field of these positions. The first position investigated is the part of the NB1 tangential channel closest to the core.

Among gamma measurements techniques, and according to the constraints arising from using this channel, it was chosen to use thermos- and optically stimulated luminescent detectors.

This paper presents the experiments carried out in September 2018 as well as their results. Three detectors types were used: TLD400 (CaF₂:Mn), TLD700 (⁷LiF:Mg,Ti) and OSLD (Al₂O₃:C). Measurements were performed in several steps: background measurements, transient measurements (divergence phase + SCRAM), and irradiation at steady state. In the end, these measurements will provide a dose as well as a gamma flux value for this position.