• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 7, 070503 (2024)
Yihan HUANG, Tiejun ZU*, Liangzhi CAO, and Hongchun WU
Author Affiliations
  • School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
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    DOI: 10.11889/j.0253-3219.2024.hjs.47.070503 Cite this Article
    Yihan HUANG, Tiejun ZU, Liangzhi CAO, Hongchun WU. Development and verification of covariance data generation module in NECP-Atlas[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070503 Copy Citation Text show less
    References

    [1] GE Zhigang, CHEN Yongjing. Research on nuclear data evaluation and development of data library[J]. Scientia Sinica (Physica, Mechanica & Astronomica), 50, 19-28(2020).

    [2] Trkov A, Brown D A. ENDF-6 formats manual: data formats and procedures for the evaluated nuclear data files[R](2008).

    [3] Chadwick M B, Obložinský P, Herman M et al. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 107, 2931-3060(2006).

    [4] Chadwick M B, Herman M, Obložinský P et al. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data[J]. Nuclear Data Sheets, 112, 2887-2996(2011).

    [5] Brown D A, Chadwick M B, Capote R et al. ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data[J]. Nuclear Data Sheets, 148, 1-142(2018).

    [6] Ge Z, Xu R, Wu H et al. CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library[J]. EPJ Web of Conferences, 239, 09001(2020).

    [7] Chiba G. ERRORJ: A code to process neutron-nuclide reaction cross section covariance, version 2.3[R](2007).

    [8] Macfarlane R, Muir D W, Boicourt R M et al[M]. The NJOY nuclear data processing system, Version 2016(2017).

    [9] LIU Ping, WU Xiaofei, LI Songyang et al. Development of multi-group constant processing software ruler[J]. Atomic Energy Science and Technology, 52, 1153-1159(2018).

    [10] YU Jiankai. Key methods and software development of evaluation, processing and application of important nuclear data for reactor[D](2015).

    [11] QIU Yishu, YU Jiankai, LIANG Jingang et al. keff sensitivity analysis to nuclear data with RMC code[J]. Atomic Energy Science and Technology, 49, 1821-1827(2015).

    [12] HUANG Jinlong, CAO Liangzhi, HE Qingming et al. Sensitivity analysis of continuous-energy nuclear data and its application in AP1000[J]. Atomic Energy Science and Technology, 56, 53-60(2022).

    [13] Aufiero M, Bidaud A, Hursin M et al. A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT[J]. Annals of Nuclear Energy, 85, 245-258(2015).

    [14] Zu T J, Xu J L, Tang Y Q et al. NECP-Atlas: a new nuclear data processing code[J]. Annals of Nuclear Energy, 123, 153-161(2019).

    [15] ZU Tiejun, XU Jialong, WU Hongchun et al. Development and validation of nuclear data processing code NECP-Atlas[J]. Atomic Energy Science and Technology, 52, 1160-1165(2018).

    [16] XU Jialong, ZU Tiejun, CAO Liangzhi et al. Development and verification of multi-group constants processing module in NECP-Atlas[J]. Nuclear Power Engineering, 40, 12-17(2019).

    [17] GAO Feng, LIU Xuqing, JIANG Hongyan[M]. Probability and mathematical statistics(2019).

    [18] LI Naicheng, MEI Liquan[M]. Numerical analysis(2011).

    [19] XU Jialong. Research on new methods of nuclear-data processing for reactor applications and development of independent nuclear-data processing code NECP-Atlas[D](2019).

    [20] Zu T J, Wan C H, Cao L Z et al. Total uncertainty analysis for PWR assembly based on the statistical sampling method[J]. Nuclear Science and Engineering, 183, 371-386(2016).

    [21] Ivanov K, Avramova M, Kodeli I A et al. Benchmark for uncertainty analysis in modeling (UAM) for design, operation and safety analysis of LWRs[R](2007).

    [22] Huang J L, Cao L Z, He Q M et al. Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX[J]. Progress in Nuclear Energy, 160, 104666(2023).

    [23] He Q M, Zheng Q, Li J et al. NECP-MCX: a hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems[J]. Annals of Nuclear Energy, 151, 107978(2021).

    [24] Briggs J B, Scott L, Nouri A. The international criticality safety benchmark evaluation project[J]. Nuclear Science and Engineering, 145, 1-10(2003).

    Yihan HUANG, Tiejun ZU, Liangzhi CAO, Hongchun WU. Development and verification of covariance data generation module in NECP-Atlas[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070503
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