ALFRED: A revised concept to improve pool related thermal-hydraulics

Frignani, Michele; Alemberti, A.; Tarantino, M.

doi:10.1016/j.nucengdes.2019.110359

Cited by 16 publications

(14 citation statements)

References 11 publications

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“…Following the completion of the ELSY project, the design and research of ALFRED (Advanced Lead Fast Reactor European Demonstrator) and ELFR (European Lead Fast Reactor) have been proposed in the frame of the EU‐FP7 LEADER (Lead cooled European Advanced Demonstration Reactor) project 12 . ALFRED is being developed vigorously at present and the construction is scheduled to be completed in Romania in 2028 13 . ELECTRA (European Lead Cooled Training Reactor) 14,15 concept has been developed for the acquisition of LFRs' operation technology and also as an educational and training facility by the KTH Royal Institute of Technology (KTH) in Sweden.…”

Section: Lead‐based Reactor Development Status Around the Worldmentioning

confidence: 99%

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Sheng

et al. 2021

Int J Energy Res

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Summary Lead‐based fast reactor is one of the most promising fourth‐generation nuclear energy systems. Fuel assembly design is a key technology for the research and development of lead‐based fast reactor. The current status of typical lead‐based reactors and fuel assembly design schemes in the world are reviewed in this paper, and also the key technical parameters and design features of fuel assembly are summarized, with the advantages and disadvantages discussed. A hexagonal fuel assembly that can achieve both “passive” and “active” axial positioning by the gravity of ballast unit and mechanical locking device proposed by the nuclear fuel assembly research group of China initiative Accelerator Driven System project at Institute of Modern Physics has been emphatically introduced. It is expected that this paper can provide certain supporting data and reference solutions for the further design and development of fuel assembly for lead‐based reactor.

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Section: Lead‐based Reactor Development Status Around the Worldmentioning

confidence: 99%

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Sheng

et al. 2021

Int J Energy Res

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“…Among various kinds of fast reactors, the lead or lead-bismuth eutectic (LBE)-cooled reactor is regarded as one of the most promising next-generation nuclear energy systems and has already been put onto the schedule for practical usage. Consequently, a variety of designs have sprung up around the world, like SVBR (Zrodnikov et al, 2011), MYRRHA (Abderrahim et al, 2001;Biarrotte et al, 2010), CLEAR (Wu, 2016a;Wu, 2016b), ALFRED (Damiani et al, 2014;Frogheri et al, 2013;Frignani et al, 2019a;Frignani et al, 2019b), etc.,…”

Section: Introductionmentioning

confidence: 99%

Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs

Fang

Guo

et al. 2020

Front. Energy Res.

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The concept of wire-wrapped assembly has been widely adopted in liquid metal-cooled reactors to enhance the capability of flow and heat transfer. The detailed 3D thermal hydraulic behaviors of liquid metal in the wire-wrapped assembly directly affect the safety of the reactor. In the present work, a numerical study on a 19-pin wire-wrapped assembly cooled by a lead-bismuth eutectic was carried out using the CFD method. The geometrical model is referred to in the test section in KIT’s 19-pin experiments, which is a scaled test assembly based on the MYRRHA reactor. The established CFD model was validated against experimental data and results showed that the SST k-ω model accompanied with the modified Prt was appropriate for the current problem. Then the numerical models were extensively used in the modeling of the blocked assembly flow with a cylindrical blockage. Also, the influences of blockage longitude, position, and porosity on the thermal hydraulic characteristics in the assembly were evaluated in detail. This work is meaningful for the deep understanding of safety features under the condition of assembly blockage operation in LFRs.

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“…Initially, the ALFRED reference concept was developed in the frame of the LEADER (Lead-cooled European Advanced DEmonstration Reactor) project, within the European 7 th Framework Programme (FP7) (Frogheri et al, 2013). In the last years, a revised concept of the reactor has been proposed, responding to main specific issues identified in the previous configuration (Frignani et al, 2019a).…”

Section: Introductionmentioning

confidence: 99%

“…At the end of the LEADER project, the common efforts between ANSALDO, the Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA) and the Institute for Nuclear Research (ICN) (Romania) were confirmed in December 2013, with the signature of FALCON (Fostering ALFRED Construction) international consortium (Frignani et al, 2019a). In this framework, a new strategic vision was conceived, aiming to accelerate the commissioning and the operation of ALFRED.…”

Section: Introductionmentioning

confidence: 99%