| Issue |
EPJ Web Conf.
Volume 170, 2018
ANIMMA 2017 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
|
|
|---|---|---|
| Article Number | 04006 | |
| Number of page(s) | 3 | |
| Section | Research reactors | |
| DOI | https://doi.org/10.1051/epjconf/201817004006 | |
| Published online | 10 January 2018 | |
https://doi.org/10.1051/epjconf/201817004006
Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor
CEA, LIST, F-91191 Gif-sur-Yvette, France phone: +33169088491 .
CEA, DEN, F-13108 Saint-Paul-les-Durance, France phone: +33442253926) .
email: romain.coulon@cea.fr
email: christian.jammes@cea.fr
Published online: 10 January 2018
Delayed neutron detection systems are key apparati in Sodium cooled Fast Reactors to prevent safety accidents. Based on the feedbacks from Phenix and Superphenix, DND systems are studied by means of the Monte-Carlo particles transport code MCNP6. Promising designs are proposed and investigated as a result of the simulation study.
Key words: Fast reactor / Sodium / Fuel failure / Fission products / Neutron detection
© The Authors, published by EDP Sciences, 2018
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. (http://creativecommons.org/licenses/by/4.0/).
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