Abstract
Dosimetry measurements were carried out during the AMMON experimental program, in the EOLE facility. Al-0.1 wt% Au wires were positioned along curved fuel plates of JHR-type assemblies to investigate the azimuthal and axial gold capture rate profiles, directly linked to the thermal and epithermal flux. After irradiation, wires were cut into small segments (a few mm), and the gold capture rate of each part was measured by gamma spectrometry on the MADERE platform. This paper presents results in the “hafnium” configuration, and more specifically the azimuthal flux profile characterization. The final uncertainty on each measured wire lies below 1% (at 2 standard deviations). Experimental profiles are in a good agreement against Monte Carlo calculations, and the 4% capture rate increase at the plate edge is well observed. The flux dissymmetry due to assembly position in the core is also measured, and shows a 10% discrepancy between the two edges of the plate.
Highlights
Al-0.1 wt% Au wires were positioned along curved fuel plates of Jules Horowitz Material Testing Reactor (JHR)-type assemblies to investigate the azimuthal and axial gold capture rate profiles, directly linked to the thermal and epithermal flux
Wires were cut into small segments, and the gold capture rate of each part was measured by gamma spectrometry on the MADERE platform
Coinducted between 2010 and 2013, the AMMON experimental program [1] in the French EOLE Zero Power Reactor located in Cadarache [2], was devoted to the experimental validation of the HORUS calculation scheme, dedicated to the future Jules Horowitz Material Testing Reactor (JHR) [3]
Summary
Coinducted between 2010 and 2013, the AMMON experimental program [1] in the French EOLE Zero Power Reactor located in Cadarache [2], was devoted to the experimental validation of the HORUS calculation scheme, dedicated to the future Jules Horowitz Material Testing Reactor (JHR) [3]. The goal of this program was to determine the biases and uncertainties associated with the calculation of the main JHR neutron safety parameters (reactivity, absorber reactivity worth, power distribution, and kintics parameters) and performance parameters (such as fast flux in the core). Experimental versus computed profiles, for several plates measured on two positions of the dismountable assembly in the AMMON core are presented
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