| Numéro |
EPJ Web Conf.
Volume 253, 2021
ANIMMA 2021 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
|
|
|---|---|---|
| Numéro d'article | 04011 | |
| Nombre de pages | 5 | |
| Section | Research Reactors and Particle Accelerators | |
| DOI | https://doi.org/10.1051/epjconf/202125304011 | |
| Publié en ligne | 19 novembre 2021 | |
https://doi.org/10.1051/epjconf/202125304011
Sensitivity Analysis of an Advanced Transmission Measurement Method for Thermal Neutrons Absorbers Detection in Irradiated Beryllium
a
NCBJ 05-400 Otwock-Świerk, Poland
b
CEA Cadarache, DES/IRESNE/DER, F-13108 Saint Paul Lez Durance, France
c
CEA Saclay, DES/EC/DSE, F-91191 Gif-sur-Yvette, France
Malgorzata.wroblewska@ncbj.gov.pl
Published online: 19 November 2021
This paper presents an advanced optimization analysis of the newly developed transmission measurement method conducted in the MARIA MTR reactor for thermal neutrons absorbers estimation in irradiated beryllium elements. Several neutron sources in combination with various thermal neutron detectors are investigated, along with the optimization of the moderating polyethylene layer to improve the signal to background ratio. It was concluded that the use of 239PuBe or 241AmB neutron source with polyethylene of 0.95 g/cm3 density and ∼4.5 cm thickness, as well as either 235U lined fission chamber or BF3 detectors are meeting the requirements for the use in the experiment.
Key words: Transmission measurements / Sensitivity analysis / neutron sources / thermal neutron detectors / beryllium
© The Authors, published by EDP Sciences, 2021
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.