| Issue |
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
|
|
|---|---|---|
| Article Number | 01009 | |
| Number of page(s) | 8 | |
| Section | Dosimetry in Research and Test Reactors and in Accelerators | |
| DOI | https://doi.org/10.1051/epjconf/201610601009 | |
| Published online | 03 February 2016 | |
https://doi.org/10.1051/epjconf/201610601009
Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor
1 CEA, DEN/DER/SPEx, Cadarache, 13108 St. Paul lez Durance, France
2 CEA, DEN/DER/SPRC, Cadarache, 13108 St. Paul lez Durance, France
a Corresponding author: adrien.gruel@cea.fr
Published online: 3 February 2016
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.
© Owned by the authors, published by EDP Sciences, 2016
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