Preliminary analysis of startup and acceleration transient characteristics of helium-xenon cooled reactor direct brayton cycle system

被引:1
|
作者
Liao, Haoyang [1 ,2 ]
Zhao, Fulong [1 ,2 ]
Bao, Hui [3 ]
Lu, Ruibo [3 ]
Tan, Sichao [1 ,2 ]
Gao, Puzhen [1 ,2 ]
Tian, Ruifeng [1 ,2 ]
机构
[1] Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Peoples R China
[2] Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equipm, Harbin 150001, Peoples R China
[3] Nucl Power Inst China, Chengdu 610231, Peoples R China
关键词
Direct Brayton cycle; Helium-xenon cooled reactor; System startup simulation; Acceleration influence characteristics; FLUID;
D O I
10.1016/j.pnucene.2024.105462
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
Helium-xenon cooled reactor direct Brayton cycle system has excellent application prospects in small nuclear power plants due to its light weight, high compactness and simple structure. The safe startup of reactor system is very important, so the system startup scheme is designed. In addition, reactor system may be affected by external acceleration during operation. Whether reactor system can operate normally and safely after being affected by acceleration and its influence characteristics are not clear. In order to verify the feasibility of the system startup scheme and explore the acceleration influence characteristics, the system analysis program was developed to simulate the system startup transient operating conditions and the transient operating conditions of reactor system under the influence of acceleration. In the research of acceleration influence characteristics, acceleration has different periods, amplitudes, types and directions, and the load state is divided into load change with system output power and constant load. The results show that the designed system startup scheme can start reactor system safely. Reactor system can ignore the influence of acceleration when it has load change with system output power ability. If the load remains constant, reactor system cannot ensure continuous and stable operation after being affected by acceleration, which has the risk of Loss of Flow Accident (LOFA). The relevant research results provide theoretical reference and support for the design of the reactor system startup scheme and the research on the influence characteristics of acceleration on reactor system.
引用
收藏
页数:18
相关论文
共 48 条
  • [41] Thermodynamic Analysis and Multiple System Layouts Comparison of the Supercritical CO2 Brayton Cycle for Sodium-cooled Fast Reactor with Offshore Scenes
    Xie, Min
    Xie, Yonghui
    Zhang, Qiuhong
    He, Yichuan
    Dong, Aihua
    Zhang, Chunwei
    Shi, Yuwen
    Yang, Qiguo
    JOINT INTERNATIONAL CONFERENCE ON ENERGY, ECOLOGY AND ENVIRONMENT ICEEE 2018 AND ELECTRIC AND INTELLIGENT VEHICLES ICEIV 2018, 2018,
  • [42] Thermodynamic analysis and preliminary design of closed Brayton cycle using nitrogen as working fluid and coupled to small modular Sodium-cooled fast reactor (SM-SFR)
    Olumayegun, Olumide
    Wang, Meihong
    Kelsall, Greg
    APPLIED ENERGY, 2017, 191 : 436 - 453
  • [43] Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR)
    Khan, Salah Ud-Din
    Wang, Jian
    Song, Yuntao
    Khan, Shahab Ud-Din
    Rana, Usman Ali
    Khan, Riaz
    JOURNAL OF FUSION ENERGY, 2018, 37 (06) : 308 - 316
  • [44] Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR)
    Salah Ud-Din Khan
    Jian Wang
    Yuntao Song
    Shahab Ud-Din Khan
    Usman Ali Rana
    Riaz Khan
    Journal of Fusion Energy, 2018, 37 : 308 - 316
  • [45] Dynamic simulation and analysis of transient characteristics of a thermal-to-electrical conversion system based on supercritical CO2 Brayton cycle in hypersonic vehicles
    Ma, Xiaofeng
    Jiang, Peixue
    Zhu, Yinhai
    APPLIED ENERGY, 2024, 359
  • [46] Loss of off-site power transient analysis for a sodium-cooled fast reactor equipped with a gas power conversion system and preliminary optimisation of its operation
    Grange, A.
    Marrel, A.
    Droin, J. B.
    Bertrand, F.
    Boutin, O.
    Ferrasse, J. H.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 355
  • [47] Thermodynamic and Dynamic Characteristics Analysis of the S-CO2 Cycle Power Generation System Integrated With Lead-bismuth Cooled Reactor for Underwater Vehicle
    Jiang T.
    Li M.
    Liang J.
    Ma T.
    Zhang H.
    Guo J.
    Zhongguo Dianji Gongcheng Xuebao/Proceedings of the Chinese Society of Electrical Engineering, 2023, 43 (11): : 4138 - 4149
  • [48] Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code
    D'Amico, Salvatore
    Di Maio, Pietro Alessandro
    Jin, Xue Zhou
    Gonzalez, Francisco Alberto Hernandez
    Moscato, Ivo
    Zhou, Guangming
    FUSION ENGINEERING AND DESIGN, 2021, 162