The water‐cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium–lead as breeder–multiplier, pressurized w...
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https://www.riss.kr/link?id=O120807733
E. Martelli ; A. Del Nevo ; P. Arena ; G. Bongiovì ; G. Caruso ; P. A. Di Maio ; M. Eboli ; G. Mariano ; R. Marinari ; F. Moro ; R. Mozzillo ; F. Giannetti ; G. Di Gironimo ; A. Tarallo ; A. Tassone ; R. Villari
2018년
-
0363-907X
1099-114X
SCIE;SCOPUS
학술저널
27-52 [※수록면이 p5 이하이면, Review, Columns, Editor's Note, Abstract 등일 경우가 있습니다.]
0
상세조회0
다운로드다국어 초록 (Multilingual Abstract)
The water‐cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium–lead as breeder–multiplier, pressurized w...
The water‐cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium–lead as breeder–multiplier, pressurized water as coolant, and EUROFER as structural material. The current design is based on DEMO 2015 specifications and represents the follow‐up of the design developed in 2015. The single‐module‐segment approach is employed. This is constituted by a basic geometry repeated along the poloidal direction. The power is removed by means of radial–toroidal (i.e., horizontal) water cooling tubes in the breeding zone. The lithium–lead flows in a radial–poloidal direction. On the back of the segment, a 100‐mm‐thick plate is in charge of withstanding the loads due to normal operation and selected postulated initiating events. Water and lithium–lead manifolds are designed and integrated with a consistent primary heat transport system, based on a reliable pressurized water reactor operating experience, and the lithium–lead system. Rationale and features of the single‐module‐segment water‐cooled lithium–lead breeding blanket design are discussed and supported by thermo‐mechanic, thermo‐hydraulic, and neutronic analyses. Preliminary integration with the primary heat transfer system, the energy storage system, and the balance of plant is briefly discussed. Open issues, areas of research, and development needs are finally pointed out. @EUROfusion Consortium*, 2017. *For more details see http://www.euro‐fusionscipub.org/disclaimer‐copyright
The paper concerns the new design of the water‐cooled lithium–lead breeding blanket, which is one of the candidate options for the European Demonstration Power Plant fusion reactor. The new design consists of a single‐module blanket segment concept and presents horizontal (i.e., radial–toroidal) water‐cooling tubes in the breeding zone, and lithium–lead flowing in the radial–poloidal direction. The paper presents the rationale and features of the water‐cooled lithium–lead breeding blanket design, supported by thermo‐mechanic, thermo‐hydraulic, magneto‐hydrodynamic, and neutronic analyses.
PREFACE for the special issue on “progress in novel nuclear energy technologies”
Cover Image, Volume 42, Issue 1