Advance Search
Volume 45 Issue 5
Oct.  2024
Turn off MathJax
Article Contents
Wu Hongwei, Xia Bing, She Ding, Li Fu, Zhang Zuoyi. Preliminary Research of Pebble Bed High-Temperature Gas-Cooled Reactor with Random Refueling Approach Based on VSOP[J]. Nuclear Power Engineering, 2024, 45(5): 1-6. doi: 10.13832/j.jnpe.2024.05.0001
Citation: Wu Hongwei, Xia Bing, She Ding, Li Fu, Zhang Zuoyi. Preliminary Research of Pebble Bed High-Temperature Gas-Cooled Reactor with Random Refueling Approach Based on VSOP[J]. Nuclear Power Engineering, 2024, 45(5): 1-6. doi: 10.13832/j.jnpe.2024.05.0001

Preliminary Research of Pebble Bed High-Temperature Gas-Cooled Reactor with Random Refueling Approach Based on VSOP

doi: 10.13832/j.jnpe.2024.05.0001
  • Received Date: 2023-10-30
  • Rev Recd Date: 2024-01-30
  • Publish Date: 2024-10-14
  • The pebble bed high-temperature gas-cooled reactor (PB-HTGR) is characterized by continuous online refueling. The fuel ball flows slowly in the core of the reactor. The VSOP code, which is widely used in engineering design, employs an approximate and average refueling method to simulate the process, tending to diminish the randomness of the pebble flow of PBR to some extent. In this paper, a new approach of random refueling based on VSOP code is proposed, and it improves the core refueling model and focuses on the impact of the average merging effect of discharging fuel. The results show that the random refueling approach can provide a more refined discharge fuel burnup probability distribution, and the average merging effect of discharging fuel tends to the broadening and overlapping of burnup peaks.

     

  • loading
  • [1]
    ZHANG Z Y, WU Z X, SUN Y L, et al. Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM[J]. Nuclear Engineering and Design, 2006, 236(5-6): 485-490. doi: 10.1016/j.nucengdes.2005.11.024
    [2]
    RÜTTEN H J, HAAS K A, BROCKMANN H, et al. V. S. O. P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009[Z]. Germany: Institut für Energieforschung, 2010.
    [3]
    RYCROFT C H, GREST G S, LANDRY J W, et al. Analysis of granular flow in a pebble-bed nuclear reactor[J]. Physical Review E, 2006, 74(2): 021306. doi: 10.1103/PhysRevE.74.021306
    [4]
    XIA B, ZHANG J, GUO J, et al. Study on the curved channel model in the initial core loading of pebble bed high temperature reactors[J]. Journal of Physics: Conference Series, 2021, 2048(1): 012025. doi: 10.1088/1742-6596/2048/1/012025
    [5]
    郝琛,李富,郭炯. 球床高温气冷堆卸料燃耗阈值对平均卸料燃耗的影响[J]. 原子能科学技术,2013, 47(S1): 188-191.
    [6]
    CHEN H, FU L, JIONG G, et al. Quantitative analysis of uncertainty from pebble flow in HTR[J]. Nuclear Engineering and Design, 2015, 295: 338-345. doi: 10.1016/j.nucengdes.2015.10.005
    [7]
    李富,经荥清,胡永明,等. 高温气冷堆物理分析程序的发展与验证[C]//第三届反应堆物理与核材料学术研讨会论文集. 北京: 清华大学工程物理系,2007: 12-13.
    [8]
    CHEN H, FU L. Investigation on the pebble bed flow model in VSOP[J]. Nuclear Engineering and Design, 2014, 271: 352-355. doi: 10.1016/j.nucengdes.2013.11.061
    [9]
    XIA B, GUO J, LI F. Impacts of burn-up measurement errors on discharge burn-up of PB-HTR[J]. Transactions, 2015, 113(1): 1287-1290.
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(4)  / Tables(1)

    Article Metrics

    Article views (107) PDF downloads(50) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return