Millimetric fuel rod displacements: an experimental study of the impact on local thermal neutron flux in the CROCUS reactor
The impact on the thermal neutron flux due to a few mm displacement of a single fuel rod in the periphery lattice of the CROCUS zero-power reactor was measured. These high-resolution experiments were carried out using a miniature neutron detector positioned in the variable inter-pin space. The experimental data obtained show that a variation of [-2.3, +2.2] ± 0.2 mm at the detector level with respect to the nominal lattice position results in a variation of the thermal neutron count rate of [+3.62, -5.47] ± 0.07%, for a total relative variation of 9.09 ± 0.07 % over 4.5 ± 0.3 mm. Serpent 2 Monte Carlo simulations were performed for comparison purposes: the deviations between relative simulations results and measurement data are in the range of ±2.1%, and within 1 to 2 standard deviations.
2-s2.0-85184961803
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
École Polytechnique Fédérale de Lausanne
2022
9780894487873
2632
2641
REVIEWED
EPFL
Event name | Event acronym | Event place | Event date |
Pittsburgh, United States | 2022-05-15 - 2022-05-20 | ||