Advance Search
Volume 42 Issue 5
Sep.  2021
Turn off MathJax
Article Contents
Wan Chenghui, Li Yunzhao, Zheng Youqi, Liu Zhouyu, Zu Tiejun, Cao Liangzhi, Wu Hongchun, Shen Wei. Code Development and Engineering Validation of PWR Fuel Management Software Bamboo-C[J]. Nuclear Power Engineering, 2021, 42(5): 15-22. doi: 10.13832/j.jnpe.2021.05.0015
Citation: Wan Chenghui, Li Yunzhao, Zheng Youqi, Liu Zhouyu, Zu Tiejun, Cao Liangzhi, Wu Hongchun, Shen Wei. Code Development and Engineering Validation of PWR Fuel Management Software Bamboo-C[J]. Nuclear Power Engineering, 2021, 42(5): 15-22. doi: 10.13832/j.jnpe.2021.05.0015

Code Development and Engineering Validation of PWR Fuel Management Software Bamboo-C

doi: 10.13832/j.jnpe.2021.05.0015
  • Received Date: 2020-07-28
  • Rev Recd Date: 2021-03-04
  • Publish Date: 2021-09-30
  • Based on the conventional “two-step” scheme for the PWR fuel management, an advanced PWR fuel management software Bamboo-C has been developed by the most advanced methodologies in the reactor-physics field. Bamboo-C consists of three main functional codes: LOCUST code for the heterogeneous modeling and simulation and homogenization calculation of 2D assemblies; SPARK code for 3D core steady-state and transient analysis; and LtoS code for assembly homogenization parameter function, which links LOCUST and SPARK. Bamboo-C has all the necessary analysis functions for the fuel management and nuclear design of PWRs, mainly including the start-up physics tests, calculations of the neutron-kinetics parameters, differential and integral worth of rod cluster control assemblies (RCCAs), and power-operation following simulation. Finally, the engineering validations of Bamboo-C have been completed according to the operation data from the reactors CNP300, CNP650 and CNP1000 designed by China independently. The validation results show that the errors between the values of such key parameters of cores as critical boron concentration, temperature coefficient, RCCA worth, and power distributions, calculated by Bamboo-C, and their measured values satisfy the corresponding engineering criterion limits.

     

  • loading
  • [1]
    GIRIEUD P, DAUDIN L, GARAT C, et al. SCIENCE Version 2: The most recent capabilities of framatome 3d nuclear code package[R]. Frence: Framatome, 2001.
    [2]
    OUISLOUMEN M, HURIN H, MAYHUE L, et al. Quantification of the two-dimensional transport code paragon[R]. USA: Westinghouse Electric Company, 2004.
    [3]
    LIU Y. ANC: A Westinghouse advanced nodal computer code[R]. USA: Westinghouse Electric Company, 2012.
    [4]
    ZU T, XU J, TANG Y, et al. NECP-Atlas: A new nuclear data processing code[J]. Annals of Nuclear Energy, 2019(123): 153-161.
    [5]
    LI Y, ZHANG B, HE Q, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice[J]. Nuclear Engineering and Design, 2018(335): 432-440.
    [6]
    YANG W, WU H, LI Y, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core[J]. Nuclear Engineering and Design, 2018(337): 279-290.
    [7]
    CHEN J, LIU Z, ZHAO C, et al. A new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy, 2018(116): 417-428.
    [8]
    ZHENG Y, DU X, XU Z, et al. SARAX: A new code for fast reactor analysis part I: Methods[J]. Nuclear Engineering and Design, 2018(340): 421-430.
    [9]
    ZHENG Y, QIAO L, ZHAI Z, et al. SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification[J]. Nuclear Engineering and Design, 2018(331): 41-53.
    [10]
    LIU Z, HE Q, ZU T, et al. The pseudo-resonant-nuclide subgroup method based on global-local self-shielding calculation scheme[J]. Nuclear Science and Technology, 2017, 55(2): 217-228.
    [11]
    PUSA M. Computing the matrix exponential in burnup calculations[J]. Nuclear Science and Engineering, 2010(164): 140-150.
    [12]
    SMITH K. Assembly homogenization techniques for light water reactor analysis[J]. Progress in Nuclear Energy, 1986(17): 303-335.
    [13]
    RHODES J, SMITH K, XU Z. CASMO-5 energy release per fission model[C]. Interlaken Switzerland: PHYSOR, 2008.
    [14]
    TRKOV A, HERMAN M, BROWN A. ENDF-6 formats manual: BNL-90365[R]. USA: Brookhaven National Laboratory, 2012.
    [15]
    DOWNAR T, XU Y, SEKER V. Theory manual for the PARCS kinetics core simulator modules[D]. USA: University of Michigan, 2009.
  • 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(13)

    Article Metrics

    Article views (563) PDF downloads(74) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return