Design and optimization of flexible decoupled high-temperature gas-cooled reactor plants with thermal energy storage

被引:1
|
作者
Saeed, Rami M. [1 ]
Novotny, Vaclav [1 ]
Cho, So-Bin [1 ,2 ]
Shigrekar, Amey [1 ]
Otani, Courtney [1 ]
Toman, Jakub [1 ]
Mikkelson, Daniel [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
[2] Univ Michigan, Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
关键词
Flexible generation; Advanced nuclear; Thermal energy storage; Dynamic analysis; Technoeconomic optimization; Dispatch optimization; Electricity prices;
D O I
10.1016/j.enconman.2024.119098
中图分类号
O414.1 [热力学];
学科分类号
摘要
Advanced nuclear power plants are well-positioned for future zero-carbon grids, however, the need for flexible power generation will be required over the traditional emphasis on baseload generation for meeting historical demands. To achieve such flexibility, this work examines viable configurations for coupling nuclear energy production with thermal energy storage. Previous designs on nuclear-thermal energy storage configurations for advanced reactor designs, which utilized reactor steam as the heat source for charging the thermal energy storage, are restricted by the heat diversion ratio and efficiency losses, thus their impacts can be limited. In this context, this study proposes configurations for fully decoupling the nuclear reactor from the power cycle and positioning the storage as an intermediate loop, thereby achieving an unconstrained heat diversion ratio and improved efficiency. Compared with a standard high-temperature gas-cooled reactor's power cycle, steady-state thermodynamic modeling and dispatch optimizations quantify the benefits of a steam reheat cycle within the fully decoupled thermal energy system to separate the plant cycle from the high-pressure primary side. These benefits are further detailed, compatible with required high-temperature and high-pressure conditions, through (1) open-source dynamic transient models that examine the impact of off-design operation on the systems, (2) the investigation of components design and costing and finally (3) sizing and dispatch optimization. The fullydecoupled design achieves a cycle efficiency of 43.1%, an enhancement over the vendor's standard efficiency of 42.2% (Xe-100 design). The proposed design offers strengthened physical barriers from the nuclear island as well as superior operational flexibility and power boosting. Dispatch optimization and market analysis reveal that thermal energy storage size is highly dependent on the peak patterns of electricity prices and the minimum generation level constraint imposed on the balance of plant. Evaluation of off-design operation demonstrates that the full decoupling design with the suggested fail-safe control mechanisms ensures a minimal impact on reactor parameters, even during rapid power ramping.
引用
收藏
页数:18
相关论文
共 50 条
  • [31] GGA HIGH-TEMPERATURE GAS-COOLED REACTOR - GENERAL DISCUSSION
    LANDIS, JW
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1973, 12 (04): : 367 - &
  • [32] PRESENT STATUS OF HIGH-TEMPERATURE GAS-COOLED REACTOR DEVELOPMENT
    SANOKAWA, K
    SAITO, S
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1987, 29 (07): : 603 - 613
  • [33] Reactor Tests of High-Temperature Gas-Cooled Fuel Rods
    Bulkin, S. Yu
    Kuz'menko, R. S.
    Loginov, D. Yu
    Romadova, E. L.
    Cherepnin, Yu S.
    Shut'ko, K., I
    Izhutov, A. L.
    Merkurisov, I. Kh
    ATOMIC ENERGY, 2021, 129 (05) : 248 - 250
  • [35] Reactor Tests of High-Temperature Gas-Cooled Fuel Rods
    S. Yu. Bulkin
    R. S. Kuz’menko
    D. Yu. Loginov
    E. L. Romadova
    Yu. S. Cherepnin
    K. I. Shut’ko
    A. L. Izhutov
    I. Kh. Merkurisov
    Atomic Energy, 2021, 129 : 248 - 250
  • [36] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Yang Chen
    Jiang-hong You
    Zhi-jiang Shao
    Ke-xin Wang
    Ji-xin Qian
    Journal of Zhejiang University-SCIENCE A, 2011, 12 : 567 - 574
  • [37] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Chen, Yang
    You, Jiang-hong
    Shao, Zhi-jiang
    Wang, Ke-xin
    Qian, Ji-xin
    JOURNAL OF ZHEJIANG UNIVERSITY-SCIENCE A, 2011, 12 (07): : 567 - 574
  • [38] High-Temperature Gas-Cooled Reactor Concept Moves Forward
    不详
    POWER, 2010, 154 (01) : 11 - 12
  • [39] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Yang CHENJianghong YOUZhijiang SHAOKexin WANGJixin QIANState Key Laboratory of Industrial Control TechnologyZhejiang UniversityHangzhou China
    Journal of Zhejiang University-Science A(Applied Physics & Engineering), 2011, (07) : 567 - 574
  • [40] Tritium Transport and Distribution in a High-Temperature Gas-Cooled Reactor
    Lee, Sung Nam
    Tak, Nam-Il
    FUSION SCIENCE AND TECHNOLOGY, 2020, 76 (03) : 238 - 245