TRU utilization and MA transmutation in thorium-based fluorinated molten salt fast reactor

D Li - Progress in Nuclear Energy, 2024 - Elsevier
In this paper, a thorium-based fluorinated molten salt fast neutron reactor is taken as the
research object, and the utilization of thorium resources, reuse of transuranic waste (TRU) …

Heat-pipe heat exchangers for salt-cooled fission and fusion reactors to avoid salt freezing and control tritium: a review

B Zohuri, S Lam, C Forsberg - Nuclear Technology, 2020 - Taylor & Francis
The fluoride-salt-cooled high-temperature reactor and some proposed fusion reactors use
clean fluoride salts as reactor coolants that have melting points above 450° C and generate …

[HTML][HTML] Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors

M Tiberga, RGG de Oliveira, E Cervi, JA Blanco… - Annals of Nuclear …, 2020 - Elsevier
Verification and validation of multi-physics codes dedicated to fast-spectrum molten salt
reactors (MSR) is a very challenging task. Existing benchmarks are meant for single-physics …

Neutronic and fuel cycle performance analysis of fluoride and chloride fuels in Molten Salt Fast Reactor (MSFR)

MA Nasr, A Zolfaghari, R Akbari, A Cammi… - … Engineering and Design, 2023 - Elsevier
The signification of fast breeder reactors as an inexhaustible source of energy has been
elucidated by many researchers. Molten Salt Reactors (MSRs) show great promise in fuel …

Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactor

M Mira, O El Hajjaji, T El Bardouni, J Al-Zain… - Annals of Nuclear …, 2023 - Elsevier
Exploiting nuclear waste transuranic (TRU) inventories could be the promising key to
developing reliable, clean, and sustainable nuclear energy. Towards this objective, different …

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

MR Altahhan, S Bhaskar, D Ziyad, P Balestra… - … Engineering and Design, 2020 - Elsevier
In this study, a hypothetical fast spectrum Liquid Fuel Molten Salt Reactor (LFMSR) core is
modeled using the multiphysics C++ code GeN-Foam (General Nuclear Foam). GeN-Foam …

New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed

B Merk, A Detkina, O Noori-kalkhoran, L Jain… - Energies, 2023 - mdpi.com
The demand for improving the nuclear waste management has since long been identified as
one of the major hurdles for widespread use of nuclear energy. Nuclear waste management …

On a long term strategy for the success of nuclear power

B Merk, D Litskevich, KR Whittle, M Bankhead… - Energies, 2017 - mdpi.com
The current generation of nuclear reactors are evolutionary in design, mostly based on the
technology originally designed to power submarines, and dominated by light water reactors …

Impacts of power density on the breeding performance of molten salt reactors

S Chen, A Zhang, C Zou, J Chen - International Journal of …, 2022 - Wiley Online Library
A liquid‐fueled molten salt reactor (MSR) can be flexibly designed with a broad range of
power density (PD) and neutron spectrum, both of which have a strong impact on the …

Improvement of a deterministic fuel management code using artificial neural network for liquid-fueled molten salt reactor

K Yu, M Cheng, X Zuo, Z Dai - Annals of Nuclear Energy, 2023 - Elsevier
The fuel management code of liquid-fueled molten salt reactor (MSR) relies on the coupling
of the neutronics code with depletion code. The deterministic method can improve the …