Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code

被引:3
|
作者
Mascari, Fulvio [1 ]
Bersano, Andrea [1 ]
Woods, Brian G. [2 ]
Reyes, Jose N. [3 ]
Welter, Kent [3 ]
Nakamura, Hideo [4 ]
机构
[1] FSN SICNUC, ENEA CR Bologna, Via Martiri Monte Sole 4, I-40129 Bologna, Italy
[2] Oregon State Univ, Dept Nucl Engn & Radiat Hlth Phys, 128 Radiat Ctr, Corvallis, OR 97331 USA
[3] NuScale Power, 1100 NE Circle Blvd, Corvallis, OR 97330 USA
[4] JAEA, Tokai, Ibaraki 3191195, Japan
关键词
Scaling; Natural circulation; TRACE; OSU-MASLWR;
D O I
10.1016/j.nucengdes.2024.113018
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
Small Modular Reactors (SMRs) adopting passive mitigation strategies are currently the most promising technology for the near term deployment of nuclear power generation. Different SMRs designs are currently under development and are, in general, characterized by some common features with the current reactors and by other features typical of their designs. Therefore, though numerous code validation study against natural circulation (NC) have been performed for large scale reactors, further analyses are necessary to characterize the capability of codes against available experimental data representative of SMR phenomenology. Though different scaling methodologies have been developed, considering the complex geometry and phenomena of a NPP, in the design of scaled-down experimental facilities it is not possible to avoid distortions, which should be limited to nondominant phenomena. Even if dominant phenomena are preserved, due to the missing data at NPP scale, the code accuracy should be tested at different scales. Therefore, in a verification and validation process, the uncertainty related to the code scaling-up capability should be addressed, for example using counter-part tests. Since NC tests at different scales in integral test facilities devoted to SMR are currently not available, a numerical scaling methodology is here proposed. Based on previous activities, having as a reference the NC DOE tests developed in the OSU-MASLWR facility, the USNRC best estimate thermal hydraulic TRACE code has been validated for simulating NC in steady and transient conditions. Since the OSU-MASLWR is volume and height scaled, the target of this paper is to assess the scaling-up capability of the OSU-MASLWR Reactor Pressure Vessel nodalization in the prediction at different scales of NC and other phenomena typical of SMR, having as a base the OSU-MASLWR-002 single phase NC data. This, also, gives some first insights about the TRACE scaling-up capability against single-phase NC in integral type configurations.
引用
收藏
页数:12
相关论文
共 35 条
  • [21] Optimal design of a Small Modular Reactor core with dual cooled annular fuel based on the neutronics and natural circulation parameters
    Nejad, M. Zaidabadi
    Ansarifar, G. R.
    NUCLEAR ENGINEERING AND DESIGN, 2020, 360
  • [22] Transient analyses on overpower transients of small modular natural circulation Lead-cooled fast reactor SNCLFR-100
    Song, Tianxin
    Zhang, Ling
    Gu, Zhixing
    Dai, Jianing
    Yu, Guanghui
    Yan, Yulin
    Zhang, Zhiwei
    KERNTECHNIK, 2025,
  • [23] SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities
    Hashim, Muhammad
    Cao, Liangzhi
    Zhou, Shengcheng
    Ma, Rubing
    Shao, Yiqiong
    Chen, Renzong
    ENERGIES, 2020, 13 (20)
  • [24] CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100
    Zhao, Pengcheng
    Shi, Kangli
    Li, Shuzhou
    Feng, Jingchao
    Chen, Hongli
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2016, 2016
  • [25] Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient
    Guo, Chao
    Zhao, Pengcheng
    Deng, Jian
    Yu, Hongxing
    Frontiers in Energy Research, 2021, 9
  • [26] Possible power increase in a natural circulation Soluble-Boron-Free Small Modular Reactor using the Truly Optimized PWR lattice
    Wijaya, Steven
    Nguyen, Xuan Ha
    Kim, Yonghee
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2023, 55 (01) : 330 - 338
  • [27] Characteristics and heating market applications of NHR200-II, a small, modular integrated full-power natural circulation reactor
    Hao W.
    Zhang Y.
    Yang X.
    Guo W.
    Qinghua Daxue Xuebao/Journal of Tsinghua University, 2021, 61 (04): : 322 - 328
  • [28] Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient
    Guo, Chao
    Zhao, Pengcheng
    Deng, Jian
    Yu, Hongxing
    FRONTIERS IN ENERGY RESEARCH, 2021, 9
  • [29] Development and application of a thermal-hydraulics analysis code for small modular natural circulation lead or lead-alloy cooled fast reactors
    Chen, Zhao
    Zhou, Guangming
    Zhao, Pengcheng
    Chen, Hongli
    ANNALS OF NUCLEAR ENERGY, 2014, 73 : 68 - 74
  • [30] CFD analyses of passive decay heat removal for the Very-Small, Long-LIfe, Modular (VSLLIM) reactor by natural circulation of ambient air
    Palomino, Luis M.
    El-Genk, Mohamed S.
    THERMAL SCIENCE AND ENGINEERING PROGRESS, 2019, 11 : 50 - 65