The innovative concept of pressurized water lead-bismuth-cooled fast reactor (PLFR) has been proposed and studied based on the previous LFR concept: PBWFR. Primary pumps and steam generators that contact lead-bismuth coolant are eliminated. A feedwater is directly injected into the primary coolant of hot lead-bismuth eutectic (LBE) at the outlet of the reactor core under the pressure of 14 MPa as PWR. The specifications of PLFR system are discussed and presented from thermal-hydraulic point of view.
- Nuclear Engineering Division
Concept of Pressurized Water Lead-Bismuth-Cooled Fast Reactor (PLFR)
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Takahashi, M. "Concept of Pressurized Water Lead-Bismuth-Cooled Fast Reactor (PLFR)." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T16A002. ASME. https://doi.org/10.1115/ICONE22-30438
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