Inherent Safety Characteristics of Lead Bismuth Eutectic-Cooled Accelerator Driven Subcritical Systems

被引:0
|
作者
Luo, Run [1 ]
Revankar, Shripad T. [2 ]
Zhang, De [1 ]
Zhao, Fuyu [3 ]
机构
[1] Univ South China, Cooperat Innovat Ctr Nucl Fuel Cycle Technol & Eq, Sch Resource & Environm & Safety Engn, Hengyang, Peoples R China
[2] Purdue Univ, Sch Nucl Engn, W Lafayette, IN USA
[3] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian, Peoples R China
关键词
accelerator driven system; neutronics; thermal-hydraulics; safety analysis; accident; HYDRAULICS COUPLED SIMULATION; PROGRAM NTC; DESIGN; REACTOR; TRANSMUTATION; VERIFICATION; NEUTRONICS; KINETICS; CODE; ADS;
D O I
10.3389/fenrg.2022.699599
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
An accelerator driven subcritical system (ADS) is a new nuclear energy system which could not only produce clean energy but also incinerate nuclear waste. In this paper, inherent safety analysis of an ADS is performed with neutronics and thermal-hydraulics coupled code named ARTAP. Five typical accidents are carried out, including the cases of proton beam interruption, transient overpower, reactivity insertion, loss of flow, and loss of heat sink. The transient simulations are performed in the average channel and the hottest channel of the fuel pin in the ADS core. The simulation results for beam interruption show that the highest temperature of the pellet is in the middle of the fuel element in the average channel, while the peak temperature of the cladding is in the top of the fuel element. After the beam is interrupted for 20s, the maximum temperature drops at the fuel center, the cladding inner surface, and the outlet coolant in the hottest channel are 644.46K, 162.27K, and 136.42K respectively. For transient overpower accidents with the increase of beam intensity, the maximum temperature of the fuel and the cladding are below the safety limit. Concerning the reactivity insertion accident, it is found that the ADS has good inherent safety and its margin of criticality safety is large. The calculation results for loss of flow show that the power drop is small due to low sensitivity of the subcritical core to negative reactivity feedback, and the maximum temperature of the cladding reaches 1726K, which means the fuel element would rupture. However, the power and the temperatures of fuel, cladding, and coolant could decrease quickly to the safety level after the proton accelerator is cut off under a loss of flow accident. The results also show that the peak temperature of the cladding is lower than the safety limit under a loss of heat sink accident. The present simulation results reveal that the ADS has a remarkable advantage against severe accidents. It also implies that its inherent safety characteristics could ensure reactor shutdown by cutting off the proton beam after accidents occur.
引用
收藏
页数:18
相关论文
共 50 条
  • [31] Experimental Investigation of the Thermal Hydraulics in Lead Bismuth Eutectic-Helium Experimental Loop of an Accelerator-Driven System
    Xi, Wenxuan
    Wang, Yongwei
    Li, Xunfeng
    Huai, Xiulan
    Cai, Jun
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (05) : 1154 - 1161
  • [32] A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor
    Nagata, Akito
    Takaki, Naoyuki
    Sekimoto, Hiroshi
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (05) : 562 - 566
  • [33] The analytical study of inventories and physicochemical configuration of spallation products produced in Lead-Bismuth Eutectic of Accelerator Driven System
    Miyahara, Shinya
    Odaira, Naoya
    Arita, Yuji
    Maekawa, Fujio
    Matsuda, Hiroki
    Sasa, Toshinobu
    Meigo, Shin-ichiro
    NUCLEAR ENGINEERING AND DESIGN, 2019, 352
  • [34] Preliminary physics study of the Lead-Bismuth Eutectic spallation target for China Initiative Accelerator-Driven System
    Zhang, Lu
    Yang, Yong-Wei
    Gao, Yu-Cui
    NUCLEAR SCIENCE AND TECHNIQUES, 2016, 27 (05)
  • [35] Solid electrolytes for use in lead-bismuth eutectic cooled nuclear reactors
    Marien, A.
    Lim, J.
    Rosseel, K.
    Vandermeulen, W.
    Van den Bosch, J.
    JOURNAL OF NUCLEAR MATERIALS, 2012, 427 (1-3) : 39 - 45
  • [36] New nuclear data libraries for lead and bismuth and their impact on accelerator-driven systems design
    Koning, A. J.
    Duijvestijn, M. C.
    van der Marck, S. C.
    Meulekamp, R. Klein
    Hogenbirk, A.
    NUCLEAR SCIENCE AND ENGINEERING, 2007, 156 (03) : 357 - 390
  • [37] Gas-phase oxygen control processes for lead/bismuth loops and accelerator driven systems
    Knebel, JU
    Müller, G
    Schumacher, G
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '99, PROCEEDINGS, 1998, : 645 - 649
  • [38] Disposition of nuclear waste using subcritical accelerator driven systems
    Voit, S
    Venneri, F
    Li, N
    Williamson, M
    Houts, M
    Lawrence, G
    PROCEEDINGS OF THE WORKSHOP ON UTILISATION AND RELIABILITY OF HIGH POWER PROTON ACCELERATORS, 1999, : 151 - 159
  • [39] Transmutations of nuclear waste in accelerator-driven subcritical systems
    Taczanowski, S
    APPLIED ENERGY, 2003, 75 (1-2) : 99 - 119
  • [40] Study on Jet Mixing Characteristics of Lead-Bismuth Eutectic Cooled Reactor Assembly Head Based on CFD Method
    Zhang, Ji
    Wang, Yingjie
    Wang, Mingjun
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (04): : 77 - 86