A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code

被引:0
|
作者
Wang, Tao [1 ]
Li, Jinggang [1 ]
Peng, Sitao [1 ]
Li, Wenhuai [1 ]
Wang, Ting [1 ]
机构
[1] China Nucl Power Technol Res Inst Co Ltd, Shenzhen 518028, Peoples R China
关键词
Nuclear fuel; Data condensation; Fuel rod performance;
D O I
10.1016/j.anucene.2024.110384
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
This note proposes a novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code. This algorithm condenses the one-dimensional data, which refines the intervals where the condensation error is large, removes the unnecessary intervals where the curvature of the data is small, and several iterations are performed to ensure the condensation error is less than the tolerance. This algorithm can reduce computation time and simplify the input of some reactor engineering software codes. Finally, two numerical examples are given to illustrate the algorithm.
引用
收藏
页数:6
相关论文
共 50 条
  • [1] The 'Fuel Rod Analysis ToolBox': A general program for preparing the input of a fuel rod performance code
    Lassmann, K.
    Schubert, A.
    van de Laar, J.
    Van Uffelen, P.
    ANNALS OF NUCLEAR ENERGY, 2015, 81 : 332 - 335
  • [2] PERFORMANCE OF A CONSTRAINED ADAPTIVE FILTERING ALGORITHM FOR DEPENDENT INPUT DATA
    KRIEGER, A
    MASRY, E
    PROCEEDINGS OF THE 22ND CONFERENCE ON INFORMATION SCIENCES AND SYSTEMS, VOLS 1 & 2, 1988, : 751 - 754
  • [3] Validation of the fuel rod performance analysis code FRIPAC
    Deng, Yong-Jun
    Wei, Jun
    Wang, Yang
    Zhang, Bin
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2019, 51 (06) : 1596 - 1609
  • [4] Assessment of Fuel Rod Performance Analysis Code FRIPAC
    Zhang B.
    Wang Y.
    Wei J.
    Deng Y.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (05): : 869 - 875
  • [5] TREQ - Fuel Rod Performance Code for Demanding PWR Plants
    Pastor, I.
    Doncel, N.
    ICONE17, VOL 5, 2009, : 183 - 191
  • [6] Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor
    Yang, Guangliang
    Guo, Zixuan
    Wang, Peng
    Wang, Weixiang
    Liao, Hailong
    Ding, Tao
    Chen, Hongli
    ANNALS OF NUCLEAR ENERGY, 2022, 171
  • [7] Analysis and Assessment of BEO-Doped Fuel with Fuel Rod Performance Code Jasmine
    China Nuclear Power Technology Research Institute Co. Ltd, Shen-Zhen, China
    Springer Proc. Phys., (87-96):
  • [8] SPEAR CODE SYSTEM - LWR FUEL ROD MECHANICAL PERFORMANCE PREDICTOR
    CHRISTENSEN, R
    ROHRER, R
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 172 - 173
  • [9] FUAS: An uncertainty and sensitivity analysis toolkit for fuel rod performance code
    Wei, Jun
    Wang, Yang
    Song, Zi-Fan
    Wang, Jie
    Liu, Xin
    Deng, Yong-Jun
    ANNALS OF NUCLEAR ENERGY, 2022, 173
  • [10] Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code
    Liao H.
    Li C.
    He Y.
    Wu Y.
    Zhang Y.
    Tian W.
    Su G.H.
    Qiu S.
    International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3 : 54 - 65