Coupling of neutronics and thermal-hydraulic of CANDU fuel management program and modification of time-averaged model

被引：0
|
作者：
Huo, Xiao-Dong [1 ]
Xie, Zhong-Sheng [1 ]
机构：
[1] Xi'an Jiaotong Univ., Xi'an 710049, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2004年 / 25卷 / 06期
关键词：
Computer software - Heavy water reactors - Nuclear power plants - Pressurized water reactors;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
In this paper, a nonlinear iteration semi-analytic nodal method to solve the diffusion equation and a steady-state single channel thermal-hydraulic code are developed and integrated in the package FMPHWR to realize the coupling of neutronics and thermal-hydraulic. Based on the experiences from PWR, a similar cross-section parameterized method to be used in CANDU is proposed to consider the feedbacks of local parameters. A modified time-averaged model is proposed on the basis of the traditional one. The numerical results show that FMPHWR has superior computational accuracy.
引用
收藏
页码：481 / 484
相关论文
共 44 条
  • [1] Development of core fuel management code system for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method
    Huo, XD
    Xie, ZS
    Liao, CK
    ANNALS OF NUCLEAR ENERGY, 2004, 31 (10) : 1083 - 1100
  • [2] Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor
    Al Zain, Jamal
    El Hajjaji, O.
    El Bardouni, T.
    Boulaich, Y.
    NUCLEAR SCIENCE AND ENGINEERING, 2019, 193 (11) : 1276 - 1289
  • [3] A HIGH EFFECTIVE PARALLEL METHOD FOR THE COUPLING BETWEEN NEUTRONICS AND THERMAL-HYDRAULIC
    Dong, Xiaomeng
    Zhang, Zhijian
    Tian, Zhaofei
    Li, Lei
    Chen, Guangliang
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016,
  • [4] Neutronics/thermal-hydraulic coupling for CSNS decoupled posioned hydrogen moderator
    Tong, J.-F., 1600, Science Press (34):
  • [5] Implementation of high-fidelity neutronics and thermal-hydraulic coupling calculations in HNET
    Zhu, Yan-Ling
    Chen, Xing-Wu
    Hao, Chen
    Wang, Yi-Zhen
    Xu, Yun-Lin
    NUCLEAR SCIENCE AND TECHNIQUES, 2022, 33 (11)
  • [6] Uncertainty Analysis of Neutronics and Thermal-hydraulic Coupling Calculation Based on CFD Code
    Yu T.
    Lei Z.
    Zhao P.
    Qian G.
    Li J.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (05): : 881 - 891
  • [7] THERMAL-HYDRAULIC CHARACTERISTICS FOR CANFLEX FUEL CHANNEL USING BURNABLE POISON IN CANDU REACTOR
    Bae, Jun Ho
    Jeong, Jong Yeob
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2015, 47 (05) : 559 - 566
  • [8] THERMAL-HYDRAULIC MODELING OF CANDU-SCWR AND LINEAR DYNAMIC MODEL DEVELOPMENT
    Sun, Peiwei
    Jiang, Jin
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 155 - 163
  • [9] Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket
    Cui, Shijie
    Zhang, Dalin
    Lian, Qiang
    Tian, Wenxi
    Cheng, Jie
    Su, G. H.
    Qiu, Suizheng
    FUSION ENGINEERING AND DESIGN, 2017, 122 : 140 - 153
  • [10] Neutronics and both analytical and numerical solutions for the rod centered subchannel thermal-hydraulic model
    Mohsen, M. Y. M.
    Abdel-Rahman, M. A. E.
    KERNTECHNIK, 2021, 86 (04) : 312 - 320
12345