Perspective Fuel Rod with Alloyed Lead in Contact Layer for Reactor BREST-OD-300
Daria Fedorovich1, Elena Ignatieva1, *, Irina Paramonova1
1Institute of Energy, Peter the Great St. Petersburg Polytechnic University (SPbPU), St. Petersburg, Russia
*Corresponding author. Email: firstname.lastname@example.org
Available Online 24 March 2022.
- 10.2991/aer.k.220308.005How to use a DOI?
- BREST-OD-300; Inherent safety; Closed nuclear fuel cycle; Fuel rod’s contact layer; Lead; Eutectic; MNUP-fuel; Outage
The article examines the temperature field of the fuel cell of the BREST-OD-300 nuclear reactor if helium in the gap between the fuel pellet and the fuel element shell is replaced with a heat-conducting Pb-Mg-Zr liquid metal layer. The temperature field is calculated for the fuel rod with the highest power density in the mode of outage. In the future BREST-OD-300 would provide a closed nuclear fuel cycle and clean energy.
- © 2022 The Authors. Published by Atlantis Press International B.V.
- Open Access
- This is an open access article under the CC BY-NC license.
Cite this article
TY - CONF AU - Daria Fedorovich AU - Elena Ignatieva AU - Irina Paramonova PY - 2022 DA - 2022/03/24 TI - Perspective Fuel Rod with Alloyed Lead in Contact Layer for Reactor BREST-OD-300 BT - Proceedings of the International Scientific and Practical Conference "Young Engineers of the Fuel and Energy Complex: Developing the Energy Agenda of the Future" (EAF 2021) PB - Atlantis Press SP - 27 EP - 32 SN - 2352-5401 UR - https://doi.org/10.2991/aer.k.220308.005 DO - 10.2991/aer.k.220308.005 ID - Fedorovich2022 ER -