Development of Lead-Cooled Fast Reactor Technologies at ENEA Brasimone Research Center

被引:0
|
作者
Martelli, Daniele [1 ]
Del Nevo, Alessandro [1 ]
Angiolini, Massimo [1 ]
Pietro, Agostini [1 ]
Tarantino, Mariano [1 ]
Grasso, Giacomo [1 ]
Lodi, Francesco [1 ]
Marinari, Ranieri [1 ]
Utili, Marco [1 ]
Sartorio, Camillo [1 ]
di Piazza, Ivan [1 ]
Diamanti, Dario [1 ]
Bassini, Serena. [1 ]
Cataldo, Sebastiano [1 ]
Lorusso, Pierdomenico [1 ]
Ciantelli, Chiara [1 ]
Cristalli, Carlo [1 ]
机构
[1] ENEA, Fus & Technol Nucl Safety & Secur Dept, I-40032 Bologna, Italy
关键词
HLM; LFR; ENEA; ALFRED; GEN IV; FALCON; CORROSION;
D O I
10.1007/s13369-024-09299-6
中图分类号
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号
07 ; 0710 ; 09 ;
摘要
In the framework of the Generation IV (GEN IV) innovative nuclear system, the ENEA Brasimone Research Center (R.C.) is at the forefront of developing Lead-cooled Fast Reactors (LFRs), one of the most promising Generation IV International Forum (GIF) concepts. ENEA's involvement in several European Atomic Energy Community (EURATOM) projects focuses on advancing Heavy Liquid Metal (HLM) technology, materials investigations, modeling, simulations, and licensing for LFRs. Since 2013, ENEA has been a full member of the Fostering ALfred CONstruction (FALCON) international consortium, partnering with Ansaldo Nucleare and RATEN-ICN to construct and operate the Advanced Lead-cooled Fast Reactor European Demonstrator (ALFRED) in Romania. This project aims to fully demonstrate LFR technology viability and expedite its market readiness. Furthermore, in 2022, ENEA and newcleo signed an agreement to develop and deploy LFRs, including constructing an electrical prototype of the newcleo LFR-AS-30, named PRECURSOR, at the ENEA Brasimone site. This prototype will facilitate studies on the thermodynamic, mechanical, and functional performance of the newcleo concept. The ENEA Brasimone Research Center hosts one of Europe's largest fleets of experimental facilities for investigating HLM thermal-hydraulics, coolant chemistry control, corrosion behavior, and material properties in HLM environments. The center also focuses on developing corrosion-protective coatings, components, instrumentation, and innovative systems, supported by experiments and numerical modeling tools. This paper provides an overview of the research activities at Brasimone Research Center, highlighting its contributions to advancing lead-cooled fast reactor design.
引用
收藏
页码:3293 / 3301
页数:9
相关论文
共 50 条
  • [41] Numerical investigation of the migration and retention of corrosion particles in a lead-cooled fast reactor
    Xu, Yishou
    Li, Xinggang
    Huang, Xiaodong
    Zhang, Xiaoxin
    Hu, Chen
    Zeng, Xian
    Yan, Qingzhi
    NUCLEAR ENGINEERING AND DESIGN, 2024, 423
  • [42] Study of construction materials for a lead-cooled reactor
    Bozin, S. N.
    Rodchenkov, B. S.
    Kashtanov, A. D.
    Markov, V. G.
    Yakovlev, V. A.
    Schenkova, I. A.
    Ivanov, Yu. A.
    Ioltukhovskiy, A. G.
    Leont'eva-Smirnova, M. V.
    ATOMIC ENERGY, 2013, 113 (05) : 320 - 326
  • [43] Status of research and development of the lead-alloy-cooled fast reactor
    Loewen, EP
    Tokuhiro, AT
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2003, 40 (08) : 614 - 627
  • [44] On the transmutation of Am in a fast lead-cooled system
    B. P. Kochurov
    V. N. Konev
    A. Yu. Kwaretzkheli
    Pramana, 2007, 68 : 193 - 199
  • [45] On the transmutation of Am in a fast lead-cooled system
    Kochurov, B. P.
    Konev, V. N.
    Kwaretzkheli, A. Yu
    PRAMANA-JOURNAL OF PHYSICS, 2007, 68 (02): : 193 - 199
  • [46] Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator
    Bortot, S.
    Moisseytsev, A.
    Sienicki, J. J.
    Artioli, Carlo
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (08) : 3021 - 3031
  • [47] Bubble transport during SGTR accident in lead-cooled fast reactor: A machine learning
    Dong, Kejian
    Khan, Shahid Ali
    He, Sihong
    Chen, Jingtan
    Ding, Peng
    Li, Wenhuai
    Song, Juqing
    Zhao, Jiyun
    NUCLEAR ENGINEERING AND DESIGN, 2023, 415
  • [48] Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core
    Xia B.
    Xu C.
    Qin T.
    Li Q.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (06): : 260 - 265
  • [49] Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor
    Xiao Luo
    Chi Wang
    Ze-Ren Zou
    Lian-Kai Cao
    Shuai Wang
    Zhao Chen
    Hong-Li Chen
    Nuclear Science and Techniques, 2022, 33
  • [50] Design and development of the power regulation system for lead-cooled fast reactor based on system modeling and fuzzy algorithm
    Shen, Yanyi
    Dong, Sifan
    Tang, Junjie
    Chen, Hongli
    ANNALS OF NUCLEAR ENERGY, 2023, 186