| Issue |
EPJ Web Conf.
Volume 211, 2019
WONDER-2018 – 5th International Workshop On Nuclear Data Evaluation for Reactor applications
|
|
|---|---|---|
| Article Number | 03003 | |
| Number of page(s) | 5 | |
| Section | Microscopic and Integral Measurements | |
| DOI | https://doi.org/10.1051/epjconf/201921103003 | |
| Published online | 05 June 2019 | |
https://doi.org/10.1051/epjconf/201921103003
An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor
1 EPFL, Laboratory for Reactor Physics and Systems behaviour (LRS), 1015 Lausanne, Switzerland
2 PSI, Laboratory for Reactor Physics and Thermal Hydraulics (LRT), 5232 Villigen, Switzerland
3 CEA/DEN, Experimental Physics, Safety & Instrumentation Division (SPESI), 13108 St-Paul-Lez-Durance, France
4 CEA/DEN, Reactor Physics and Fuel Cycle Division (SPRC), 13108 St-Paul-Lez-Durance, France
5 PSI, Nuclear Energy and Safety Research Division (NES), 5232 Villigen, Switzerland
* Corresponding author: vincent.lamirand@epfl.ch
Published online: 5 June 2019
The PETALE experimental programme in the CROCUS reactor at EPFL intends to contribute to the validation and improvement of neutron nuclear data in the MeV energy range for stainless steel, particularly in the prospect of heavy reflector elements of pressurized water reactors. It mainly consists of several transmission experiments: first, through metallic sheets of nuclear-grade stainless steel interleaved with dosimeter foils, and, successively, through its elemental components of interest – iron, nickel, and chromium. The present article describes the study for optimizing the response of the dosimetry experiments to the nuclear data of interest.
© The Authors, published by EDP Sciences, 2019
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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