Safety evaluation of supercritical CO2 cooled micro modular reactor

被引:43
|
作者
Oh, Bong Seong [1 ]
Ahn, Yoon Han [2 ]
Yu, Hwanyeal [1 ]
Moon, Jangsik [1 ]
Kim, Seong Gu [1 ]
Cho, Seong Kuk [1 ]
Kim, Yonghee [1 ]
Jeong, Yong Hoon [1 ]
Lee, Jeong Ik [1 ]
机构
[1] Korea Adv Inst Sci & Technol, Dept Nucl & Quantum Engn, 291 Daehak Ro, Daejeon 305701, South Korea
[2] Korea Atom Energy Res Inst, 1045 Daedeok Daero, Daejeon 305353, South Korea
关键词
S-CO2 cooled micro modular reactor; Control logic; Safety analysis; GAMMA plus code; BRAYTON CYCLE; PERFORMANCE;
D O I
10.1016/j.anucene.2017.08.038
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
To meet the energy requirement for a remote and isolated region, a concept of supercritical CO2 (S-CO2) cooled micro modular reactor (MMR) has been developed, which is easy to transport by fully modularizing the nuclear power system. From the previous work, only the on-design performances Of MMR were presented. However, since the nuclear system needs to meet high safety standard, the design can be finalized only after the evaluation of the nuclear system response under multiple transient conditions. Such transient conditions may include part load operation and postulated accidents. The system response can be evaluated only with a high fidelity computer simulation, since it is almost impossible to construct a nuclear facility to test at such conditions. The simulation is performed to guarantee its autonomous operability and safety. Unfortunately, a system analysis computer code available for the S-CO2 cycle analysis is yet to be developed for the MMR safety evaluation. Description of a S-CO2 system analysis code platform is first presented in this paper. After that, the developed code is validated with experimental data. The steady state of MMR is first modeled with the code, which is followed by simulations of part load operation and postulated accidents of MMR. All simulation results show that the current design of MMR has the ability to maintain its safety and structural integrity even under extreme conditions to protect the public from radiation hazard at all times. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:1202 / 1216
页数:15
相关论文
共 50 条
  • [11] Design and evaluation of control strategies and control methods for supercritical CO2 Brayton cycle directly cooled reactor system
    Jillani, Ghulam
    Shan, Jianqiang
    Xue, Qi
    Liu, Weihua
    Wu, Pan
    APPLIED THERMAL ENGINEERING, 2025, 264
  • [12] EVALUATION OF RADIATION HEAT TRANSFER IN POROUS MEDIA Application for a pebble bed modular reactor cooled by CO2 gas
    Sidi-Ali, Kamel
    Oukil, Khaled
    Hassani, Tinhinane
    Amri, Yasmina
    Alem, Abdelmoumane
    NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2013, 28 (02): : 118 - 127
  • [13] CONCEPTUAL DESIGN AND FEASIBILITY ANALYSIS OF A MODULAR SUPERCRITICAL CO2 FAST REACTOR CORE
    Lai, Guihua
    Wang, Tian
    She, Ding
    Wang, Hong
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 4, ICONE31 2024, 2024,
  • [14] Supercritical CO2 Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver
    Wu, Pan
    Gao, Chuntian
    Huang, Yanping
    Zhang, Dan
    Shan, Jianqiang
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2020, 2020
  • [15] Safety analysis of supercritical water-cooled reactor
    Qi, Bing-Xue
    Yu, Ji-Yang
    Qi, B.-X., 1600, Atomic Energy Press (46): : 669 - 673
  • [16] OPTIMAL DESIGN OF SUPERCRITICAL CO2 POWER CYCLE FOR HIGH TEMPERATURE GAS-COOLED REACTOR
    Zhou, Yujia
    Zhang, Yifan
    Li, Hongzhi
    Yao, Mingyu
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 6, ICONE31 2024, 2024,
  • [17] System Performance Analyses of Supercritical CO2 Brayton Cycle for Sodium-Cooled Fast Reactor
    Xie, Min
    Cheng, Jian
    Ren, Xiaohan
    Wang, Shuo
    Che, Pengcheng
    Zhang, Chunwei
    ENERGIES, 2022, 15 (10)
  • [18] Transient analysis of the safety characteristics on a super carbon-dioxide cooled micro modular reactor
    Liu, Limin
    Zhu, Dahuan
    Liu, Maolong
    Li, Dengwei
    Fu, Junsen
    Guo, Hui
    Xiao, Yao
    Gu, Hanyang
    NUCLEAR ENGINEERING AND DESIGN, 2024, 417
  • [19] DEVELOPMENT OF A SUPERCRITICAL CO2 BRAYTON ENERGY CONVERSION SYSTEM COUPLED WITH A SODIUM COOLED FAST REACTOR
    Cha, Jae-Eun
    Lee, Tae-Ho
    Eoh, Jae-Hyuk
    Seong, Sung-Hwan
    Kim, Seong-O
    Kim, Dong-Eok
    Kim, Moo-Hwan
    Kim, Tae-Woo
    Suh, Kyun-Yul
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (08) : 1025 - 1044
  • [20] Mass optimization of a supercritical CO2 Brayton cycle with a direct cooled nuclear reactor for space surface power
    Sondelski, Becky
    Nellis, Greg
    APPLIED THERMAL ENGINEERING, 2019, 163