Study on long-life sodium cooled fast reactor concept with radial shuffling

被引：0
|
作者：
Li, Zhipeng [1 ]
Zheng, Youqi [1 ]
Cao, Liangzhi [1 ]
机构：
[1] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an,710049, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2014年 / 35卷
关键词：
This paper proposes a core shuffling design for a long-life sodium cooled fast reactor. Based on the breed and burn strategy and by means of radial shuffling; the reactor can sustain critical for a long time without refueling. In this design concept; one-through fuel cycle is adopted for nuclear non-proliferation; heterogeneous core is considered to flatten the local power peak and to enhance the in-core breeding; inward-convergent shuffling is employed to extend the core life. Preliminary calculations had proved that the shuffling scheme is feasible. The core life can reach over 38 years and the discharged breed assemblies can be used as the driver fuel in another reactor. The key parameters of the core are within the acceptable range in current fast reactor designs. ©; 2014; Yuan Zi Neng Chuban She. All right reserved;
D O I：
10.13832/j.jnpe.2014.S2.0044
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：44 / 47
相关论文
共 50 条
  • [41] SODIUM-COOLED FAST REACTOR (SFR) SAFETY
    Sofu, Tanju
    INTERNATIONAL SEMINAR ON NUCLEAR WAR AND PLANETARY EMERGENCIES, 43RD SESSION, 2011, : 123 - 129
  • [42] A summary of sodium-cooled fast reactor development
    Aoto, Kazumi
    Dufour, Philippe
    Yang Hongyi
    Glatz, Jean Paul
    Kim, Yeong-il
    Ashurko, Yury
    Hill, Robert
    Uto, Nariaki
    PROGRESS IN NUCLEAR ENERGY, 2014, 77 : 247 - 265
  • [43] STUDY ON RADIAL THERMAL-HYDRAULIC CHARACTERISTICS OF ONCE-THROUGH STEAM GENERATOR OF SODIUM-COOLED FAST REACTOR
    Liu, Yapeng
    Wang, Bo
    Zhang, Dalin
    Feng, Zhenyu
    Li, Xinyu
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
  • [44] Conceptual Design of a Reduced Moderation Long-Life Heavy Water Cooled Thorium Small Modular Reactor
    Sun Q.
    Wang L.
    Zhang T.
    Li X.
    Liu X.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 (02): : 23 - 28
  • [45] Numerical study on the main coolant pump of sodium-cooled fast reactor
    Ko, Sungho
    Kim, Yeon-tae
    PROCEEDINGS OF THE ASME/JSME/KSME JOINT FLUIDS ENGINEERING CONFERENCE, 2015, VOL 1A, SYMPOSIA, PT 2, 2016,
  • [46] A comparative physics study for an innovative sodium-cooled fast reactor (iSFR)
    Hartanto, Donny
    Kim, Chihyung
    Kim, Yonghee
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (01) : 151 - 162
  • [47] Experimental study on sodium-concrete reaction mechanism in sodium-cooled fast reactor
    1600, Japan Society of Mechanical Engineers (79):
  • [48] Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling
    Hoang, Van Khanh
    Sambuu, Odmaa
    Nishiyama, Jun
    Obara, Toru
    NUCLEAR SCIENCE AND ENGINEERING, 2022, 196 (01) : 109 - 120
  • [49] A NEW CONCEPT FOR THE SODIUM-COOLED FAST BREEDER
    ZIEGLER, A
    BRENNSTOFF-WARME-KRAFT, 1983, 35 (1-2): : 50 - 55
  • [50] DEVELOPMENT OF AN INNOVATIVE PLATE-TYPE SG FOR SODIUM COOLED FAST REACTOR - CONCEPT AND TEST FABRICATION
    Nishi, Yoshihisa
    Kinoshita, Izumi
    ICONE 16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 4, 2008, : 309 - 317
12345