Numerical investigation of heat transfer enhancement in helically coiled specifically-shaped tube heat exchangers

P Xu, T Zhou, J Xing, Z Fu - Nuclear Engineering and Design, 2022 - Elsevier
The shape of helically coiled tube (HCT) has a profound effect on the heat transfer capability
of HCT heat exchangers (HEs). In this study, the thermo-hydraulic characteristics of two …

Liquid metal cooled fast reactor thermal hydraulic research development: A review

KT Agbevanu, SK Debrah, EM Arthur, E Shitsi - Heliyon, 2023 - cell.com
The growing interest in fast reactors demands further innovative technologies to enhance
their safety and reliability. Understanding thermal hydraulic activities required for advanced …

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 …

Heat transfer evaluation of liquid lead-bismuth eutectic cross flow tube bundle: Experimental part

Y Yang, C Wang, D Zhang, S Qiu, G Su… - International Journal of …, 2023 - Elsevier
Helical coil once-through tube steam generator (HCOTSG) is an excellent form of heat
exchanger. HCOTSG is adopted in various industries, such as Lead-bismuth Fast Reactor …

Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors

J Pacio, K Van Tichelen, S Eckert, T Wondrak… - … Engineering and Design, 2022 - Elsevier
Abstract Heavy-liquid metals (HLMs), such as lead and lead–bismuth eutectic (LBE), are
proposed as primary coolants in accelerator driven systems and next-generation fast …

[HTML][HTML] Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

A Pucciarelli, A Toti, D Castelliti, F Belloni… - Annals of Nuclear …, 2021 - Elsevier
This work aims to review the general guidelines to be adopted to perform coupled System
Thermal Hydraulics (STH)/CFD calculations. The coupled analysis is often required when …

Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator

Y Yang, Y Li, C Wang, T Wang, Z Lan, D Zhang… - … Engineering and Design, 2021 - Elsevier
Abstract Lead-bismuth Fast Reactor (LFR) has attracted attentions due to its intrinsic
characteristics, such as sustainability, safety, and economics. Helical coil once-through tube …

Design of a Novel Test Section for the Lead Fast Reactors Development: The CIRCE-THETIS Facility

P Lorusso, I Di Piazza, D Martelli… - International …, 2021 - asmedigitalcollection.asme.org
Within the R&D program of Generation IV lead fast reactors and Accelerator-Driven Systems,
a new project named PATRICIA (EC–H2020) has been launched by the European …

State-of-the-art review of the T/H system codes RELAP5 for HLM applications

P Lorusso, M Polidori, A Del Nevo, C Lombardo… - … Engineering and Design, 2023 - Elsevier
Thermal-hydraulic code RELAP5, originally developed by INEEL under NRC contract for
LWRs LOCA analysis, has been extensively validated and it is actually used worldwide as a …

STH/CFD coupled simulation of the protected loss of flow accident in the CIRCE-HERO facility

P Andrea, G Francesco, M Marigrazia, M Daniele… - Applied Sciences, 2020 - mdpi.com
The paper presents the application of a coupling methodology between Computational Fluid
Dynamics (CFD) and System Thermal Hydraulic (STH) codes developed at the University of …