Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

被引:6
|
作者
Bhowmik, P. K. [1 ]
Sabharwall, P. [1 ]
Johnson, J. T. [1 ]
Retamales, M. E. T. [1 ]
Wang, C. [1 ]
'Brien, J. E. [1 ]
Lietwiler, C. [2 ]
Wu, Q. [3 ]
机构
[1] Idaho Natl Lab, Reactor Syst Design & Anal Div, Idaho Falls, ID 83415 USA
[2] Holtec Int, Nucl Sci & Engn, Camden, NJ USA
[3] Oregon State Univ, Nucl Sci & Engn, Corvallis, OR USA
关键词
Scaled testing; Scaling methods; Similarity principles; Small modular reactor; Natural circulation; SINGLE-PHASE; SYSTEM; FLOW; LAWS;
D O I
10.1016/j.nucengdes.2024.113235
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) represent a promising option for providing clean and sustainable energy due to their potential for enhanced safety, reduced capital costs, and increased siting flexibility. However, new reactor systems require the development and operation of representative scaled-down test facilities to support the verification and validation of system computer codes and models. This study reviews the research on scaling methodologies and similarity principles pivotal in developing non-nuclear integral effects test and separate effects test facilities for water-cooled SMRs. The study focuses on a review of the scaling methods, similarity approaches, and possible challenges posed by the unique and compact design features of integral-pressurized water reactor-type SMRs, and their representative test facilities. This study also reviews previous research related to scaling and similarity methodologies and provides insights into design considerations for achieving prototypic conditions in test facilities. The findings and recommendations emphasize the broader impact of appropriate scaling and similarity principles to ensure meaningful and transferable results from non-nuclear test facilities to accelerate the safe and efficient deployment of next-generation water-cooled SMRs.
引用
收藏
页数:15
相关论文
共 12 条
  • [1] Neutronics and thermal hydraulics analysis of a small modular reactor
    Kitcher, Evans D.
    Chirayath, Sunil S.
    ANNALS OF NUCLEAR ENERGY, 2016, 97 : 232 - 245
  • [2] PILLAR: Integral test facility for LBE-cooled passive small modular reactor research and computational code benchmark
    Shin, Yong-Hoon
    Park, Jaeyeong
    Hur, Jungho
    Jeong, Seongjin
    Hwang, Il Soon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (11) : 3580 - 3596
  • [3] THERMAL-HYDRAULICS DESIGN OF WATER-COOLED PRESSURE TUBE BLANKET FOR A FUSION DRIVEN SUBCRITICAL REACTOR
    Gao, Xinli
    Zu, Tiejun
    Wu, Hongchun
    Qiu, Suizheng
    Su, Guanghui
    Tian, Wenxi
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 5, 2012, : 569 - 576
  • [4] Scaling analysis of the pressure suppression containment test facility for the small pressurized water reactor
    Liu, Xinxing
    Qi, Xiangjie
    Zhang, Nan
    Meng, Zhaoming
    Sun, Zhongning
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (03) : 793 - 803
  • [5] New stage on the neutronics and thermal hydraulics analysis of a small modular reactor core
    García J.A.R.
    Betancourt M.C.
    Hernández C.R.G.
    Rojas L.
    De Oliveira Lira C.A.B.
    De Lima Bezerra J.
    García, Jesús Alberto Rosales (jrosales@instec.cu), 2018, Inderscience Publishers, 29, route de Pre-Bois, Case Postale 856, CH-1215 Geneva 15, CH-1215, Switzerland (12) : 400 - 417
  • [6] 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
  • [7] Analysis of neutron physics and thermal hydraulics for fuel assembly of small modular reactor loaded with ATFs
    Yu, Honghao
    Cai, Jiejin
    He, Sihong
    Li, Xuezhong
    ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [8] Analysis of heat-loss mechanisms with various gases associated with the surface emissivity of a metal containment vessel in a water-cooled small modular reactor
    Lee, Geon Hyeong
    Park, Jae Hyung
    Jeong, Beomjin
    Kim, Sung Joong
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (08) : 3043 - 3066
  • [9] Development of a thermal-hydraulic analysis code for primary system of an integrated small modular pressurized water reactor
    Wang, Dongqing
    Chen, Huandong
    Chen, Jiayue
    Zhan, Dekui
    Xia, Shaoxiong
    ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [10] Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code
    Alzaben, Y.
    Sanchez-Espinoza, V. H.
    Stieglitz, R.
    ANNALS OF NUCLEAR ENERGY, 2019, 134 : 114 - 124