Review of thermal-hydraulic issues and studies of lead-based fast reactors

Y Zhang, C Wang, Z Lan, S Wei, R Chen, W Tian… - … and Sustainable Energy …, 2020 - Elsevier
The lead-based reactor is one of the fourth-generation nuclear energy systems with
excellent development prospects. It has attracted much attention because of its unique …

Role of thorium in the Indian nuclear power programme

PK Vijayan, V Shivakumar, S Basu, RK Sinha - Progress in Nuclear Energy, 2017 - Elsevier
In the context of Indian nuclear power programme, thorium has always had a prominent
place due to its unique resource position with large thorium deposits and limited uranium …

Overview on lead-cooled fast reactor design and related technologies development in ENEA

M Tarantino, M Angiolini, S Bassini, S Cataldo… - Energies, 2021 - mdpi.com
The next generation of nuclear energy systems, also known as Generation IV reactors, are
being developed to meet the highest targets of safety and reliability, sustainability …

Coupled simulations of the NACIE facility using RELAP5 and ANSYS FLUENT codes

D Martelli, N Forgione, G Barone, I Di Piazza - Annals of Nuclear Energy, 2017 - Elsevier
This work deals with the development and preliminarily assessment of a coupling
methodology between a modified version of RELAP5/Mod3. 3 STH code and FLUENT …

A novel Ansys CFX–RELAP5 coupling tool for the transient thermal-hydraulic analysis of liquid metal systems

PC Puviani, T Del Moro, B Gonfiotti, D Martelli… - Progress in Nuclear …, 2025 - Elsevier
Thermal-hydraulic analysis of three-dimensional systems and phenomena is essential for
the design and safety assessment of new Generation IV reactor concepts. While System …

Thermophysical characteristics of liquid metal In-Bi-Sn eutectic (Field's metal) as a similarity coolant

A Lipchitz, G Harvel… - Journal of Nuclear …, 2022 - asmedigitalcollection.asme.org
This work investigated the thermophysical characteristics of liquid indium–bismuth–tin
eutectic alloy also known as Field's Metal for the purposes of use as a similar fluid for liquid …

Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility

R Zhang, D Zhang, Y Liang, J Wang, J Deng… - Annals of Nuclear …, 2024 - Elsevier
Based on the experimental campaign performed on the NACIE-UP (NAtural Circulation
Experiment-Upgraded) facility, the benchmark activity was proposed by ENEA to qualify and …

E-SCAPE: a scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations

K Van Tichelen, F Mirelli, M Greco, G Viviani - Nuclear Engineering and …, 2015 - Elsevier
Abstract MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a
flexible fast-spectrum research reactor under design at SCK· CEN. MYRRHA is a pool-type …

Uncertainty quantification method for RELAP5-3D© using RAVEN and application on NACIE experiments

V Narcisi, P Lorusso, F Giannetti, A Alfonsi… - Annals of Nuclear …, 2019 - Elsevier
The best estimate plus uncertainty (BEPU) method plays a key role in the development of
the innovative Generation IV nuclear reactors, for the improvement of knowledge and the …

New steam generation system for lead-cooled fast reactors, based on steam re-circulation through ejector

L Damiani, R Revetria - Applied energy, 2015 - Elsevier
Abstract The EBBSG (External Boiling Bayonet Steam Generator) system, proposed in
previous publications, offers an alternative to the classical once-through high pressure …