2022
DOI: 10.3390/app13010482
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Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design

Abstract: The Water-Cooled Lithium–Lead (WCLL) is one of the most promising technologies for power conversion and tritium production in future fusion-powered reactors; it will be implemented in one of the Test Breeding Modules (TBM) inside the ITER reactor and the DEMO EU reactor. However, the simultaneous presence in the system of high-temperature PbLi and high-pressure water poses significant safety issues in the event of an in-box LOCA (Loss Of Coolant Accident). For this reason, a complete understanding of the syste… Show more

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Cited by 5 publications
(3 citation statements)
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“…LIFUS5/Mod4 is a PbLi facility aimed at the investigation of the PbLi-water interaction [9] at TBM scale to validate numerical models and tools currently adopted for modelling this phenomenon [10]. Indeed, one of the main concerns in terms of safety of the WCLL BB/TBM is the occurrence of an in-box Loss Of Coolant Accident (LOCA) due to the rupture of a cooling tube dived in the PbLi.…”
Section: W-hydra Experimental Platformmentioning
confidence: 99%
“…LIFUS5/Mod4 is a PbLi facility aimed at the investigation of the PbLi-water interaction [9] at TBM scale to validate numerical models and tools currently adopted for modelling this phenomenon [10]. Indeed, one of the main concerns in terms of safety of the WCLL BB/TBM is the occurrence of an in-box Loss Of Coolant Accident (LOCA) due to the rupture of a cooling tube dived in the PbLi.…”
Section: W-hydra Experimental Platformmentioning
confidence: 99%
“…With this purpose, a new integral test facility, named LIFUS5/Mod4, is being constructed at ENEA RC Brasimone [24], designed to be as representative as possible of the WCLL TBS PbLi loop [41]. The main expected scientific outcomes and technological advancements of this facility include:…”
Section: Integral Test Facility Lifus5/mod4 For the Wcll In-box Loca ...mentioning
confidence: 99%
“…The addressing of postulated in-box LOCA events by means of an approach that permits prevention of the occurrence, evaluation of the consequences, and investigation of countermeasures to mitigate the transient. This last point requires extensive numerical simulations and appropriate tools, i.e., the development of a coupling technique to perform transient analyses considering the chemical, thermo-hydraulic, and structural effects due to PbLi/water interaction [17][18][19][20][21] and numerical code to expand the simulation capabilities in fusion applications [22,23], validated against Integral Test Facility experiments [24] currently in progress as part of the FP9 Project.…”
mentioning
confidence: 99%