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CENDL-3.2与ENDF/B-Ⅷ.0的56Fe评价截面对屏蔽计算影响研究

张斌 马续波 胡馗 陈义学 吴海成

张斌, 马续波, 胡馗, 陈义学, 吴海成. CENDL-3.2与ENDF/B-Ⅷ.0的56Fe评价截面对屏蔽计算影响研究[J]. 核动力工程, 2022, 43(1): 57-63. doi: 10.13832/j.jnpe.2022.01.0057
引用本文: 张斌, 马续波, 胡馗, 陈义学, 吴海成. CENDL-3.2与ENDF/B-Ⅷ.0的56Fe评价截面对屏蔽计算影响研究[J]. 核动力工程, 2022, 43(1): 57-63. doi: 10.13832/j.jnpe.2022.01.0057
Zhang Bin, Ma Xubo, Hu Kui, Chen Yixue, Wu Haicheng. Research on the Influence of 56Fe Evaluation Cross Section of CENDL-3.2 and ENDF/B-Ⅷ.0 on Shielding Calculation[J]. Nuclear Power Engineering, 2022, 43(1): 57-63. doi: 10.13832/j.jnpe.2022.01.0057
Citation: Zhang Bin, Ma Xubo, Hu Kui, Chen Yixue, Wu Haicheng. Research on the Influence of 56Fe Evaluation Cross Section of CENDL-3.2 and ENDF/B-Ⅷ.0 on Shielding Calculation[J]. Nuclear Power Engineering, 2022, 43(1): 57-63. doi: 10.13832/j.jnpe.2022.01.0057

CENDL-3.2与ENDF/B-Ⅷ.0的56Fe评价截面对屏蔽计算影响研究

doi: 10.13832/j.jnpe.2022.01.0057
基金项目: 国家自然科学基金项目(11875128)
详细信息
    作者简介:

    张 斌(1995—),男,博士,现主要从事核数据方面的研究,E-mail: wenwubingo@163.com

    通讯作者:

    马续波,E-mail: maxb917@163.com

  • 中图分类号: TL328;TL329+.3;TL341

Research on the Influence of 56Fe Evaluation Cross Section of CENDL-3.2 and ENDF/B-Ⅷ.0 on Shielding Calculation

  • 摘要: CENDL-3.2评价库对56Fe非弹性散射截面进行了更新,为了验证其与ENDF/B-Ⅷ.0评价库中截面以及屏蔽计算能力的差异,通过NJOY2016程序对56Fe共振重造后的非弹性散射、总截面等微观截面进行了比较;并制作了多群截面,在56Fe非弹性散射能量范围对以56Fe为主要核素的3个系列屏蔽基准题ILL-Fe、OKTAVIAN-Fe、IPPE-Fe进行了屏蔽计算性能的比较。结果表明,CENDL-3.2评价库的非弹性散射截面在4~12 MeV能量范围内低于ENDF/B-Ⅷ.0评价库的结果;多群截面基准题验证表明,CENDL-3.2评价库计算结果与实验值总体符合较好;对于OKTAVIAN-Fe基准题,在0.1~1 MeV能量范围内两评价库计算结果吻合较好。此外,所有基准题验证结果都有共同的现象,即在56Fe非弹性散射截面占主要贡献的1~10 MeV能量范围内,CENDL-3.2的计算结果比ENDF/B-Ⅷ.0的计算结果偏高。

     

  • 图  1  CENDL-3.2库与ENDF/B-Ⅶ.1库、ENDF/B-Ⅷ.0库56Fe微观截面结果对比

    1 b=10−24cm2

    Figure  1.  Comparison of the Results of 56Fe Micro Cross-section between CENDL-3.2, ENDF/B-Ⅶ.1 and ENDF/B-Ⅷ.0 Libraries

    图  2  MATXS格式多群截面数据库制作及验证流程

    Figure  2.  The Process of MATXS Format Multi-group Cross-section Library Production and Verification

    图  3  OKTAVIAN-Fe基准计算值与实验值对比图

    Figure  3.  Comparison of the Calculated and Experimental Values of OKTAVIAN-Fe Benchmark

    图  4  ILL-Fe基准题计算值与实验值对比图

    Figure  4.  Comparison of the Calculated and Experimental Values of ILL-Fe Benchmark

    图  5  IPPE-Fe基准题模型几何结构图

    Figure  5.  Geometric Structure of IPPE-Fe Benchmark Model

    图  6  IPPE-Fe基准计算值与实验值对比图

    Figure  6.  Comparison of the Calculated and Experimental Values of IPPE-Fe Benchmark

    图  7  IPPE-Fe基准题3的CENDL-3.2计算结果与ENDF/B-Ⅷ.0计算结果比值

    Figure  7.  Ratio of Results of CENDL-3.2 to ENDF/B-Ⅷ.0 for the IPPE-Fe Benchmark 3

    表  1  OKTAVIAN-Fe屏蔽装置材料组成

    Table  1.   Material Composition of OKTAVIAN-Fe Shielding Device

    元素核子密度/(b−1·cm−1)
    Fe8.3579×10−2
    Mn7.6620×10−4
    Si3.8732×10−4
    C6.3004×10−4
    P3.0540×10−5
    S1.4749×10−5
    下载: 导出CSV

    表  2  ILL-Fe基准模型物理参数描述

    Table  2.   Description of Physical Parameters of ILL-Fe Benchmark Model

    参数名参数值
    球壳外半径/cm 38.1
    球壳内半径/cm 7.65
    密度 /(g·cm−3) 7.87
    核子密度/ (b−1·cm−1) 0.0849
    下载: 导出CSV

    表  3  IPPE-Fe基准题几何参数和核子密度

    Table  3.   Geometric Parameters and Nucleon Density of IPPE-Fe Benchmark

    基准题球壳几何参数中子平均自由程/m核子密度/(b−1·cm−1)径向孔参数ri (li)/ cm(V’/V)平均值/%
    R/cmr/cm壁厚/cm
    1 4.5 2.0 2.5 0.5 840 2.0(2.5) 10.6
    2 12.0 4.5 7.5 1.6 820 3.2(4), 3.0(3.5) 3.3
    3 20.0 1.9 18.1 3.9 830 2.5(10.3), 1.9(7.8) 0.9
    4 30.0 2.0 28.0 6.1 830 4(7), 2.5(7.8), 2.0(13.2) 0.6
    下载: 导出CSV
  • [1] LEE C, YANG W S. MC2-3: multigroup cross section generation code for fast reactor analysis[J]. Nuclear Science and Engineering, 2017, 187(3): 268-290. doi: 10.1080/00295639.2017.1320893
    [2] WENNER M T, HAGHIGHAT A, ADAMS J M, et al. Novel investigation of iron cross sections via spherical shell transmission measurements and particle transport calculations for material embrittlement studies[J]. Nuclear Science and Engineering, 2017, 170(3): 207-233.
    [3] CHADWICK M B, DUPONT E, BAUGE E, et al. The CIELO collaboration: neutron reactions on 1H, 16O, 56Fe, 235, 238U, and 239Pu[J]. Nuclear Data Sheets, 2014, 118: 1-25. doi: 10.1016/j.nds.2014.04.002
    [4] 钱晶,葛智刚,刘廷进,等. 20MeV以下快中子与56Fe非弹性散射截面的分歧研究[J]. 原子核物理评论,2017, 34(3): 514-519. doi: 10.11804/NuclPhysRev.34.03.514
    [5] GE Z G, XU R R, WU H C, et al. CENDL-3.2: The new version of Chinese general purpose evaluated nuclear data library[J]. EPJ Web of Conferences, 2020, 239: 09001. doi: 10.1051/epjconf/202023909001
    [6] 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, 2011, 112(12): 2887-2996. doi: 10.1016/j.nds.2011.11.002
    [7] 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, 2018, 148: 1-142. doi: 10.1016/j.nds.2018.02.001
    [8] MACFARLANE R, MUIR D W, BOICOURT R M, et al. The NJOY nuclear data processing system, version 2016: LA-UR-17-20093[R]. Los Alamos, United States: Los Alamos National Laboratory, 2017.
    [9] MACFARLANE R E. TRANSX 2: a code for interfacing MATXS cross-section libraries to nuclear transport codes: LA-12312-MS[R]. NM, United States: Los Alamos National Laboratory, 1992
    [10] ENGLE JR W W. A users manual for ANISN: a one dimensional discrete ordinates transport code with anisotropic scattering: K-1693 [R]. United States: Oak Ridge Gaseous Diffusion Plant, 1967
    [11] SUMITA K, TAKAHASHI A, HASHIKURA H, et al. Measurements of neutron leakage spectra from 50.32 cm radius iron sphere: A-83-07[R]. Japan: Osaka University, 1983.
    [12] HASHIKURA H, HAIKAWA K, TAKAHASHI A, et al. Neutron leakage spectra from a large iron sphere pulsed with 14 MeV neutrons[C]//Proceedings of the NEA Specialists' Meeting on Shielding Benchmarks, Saclay, France, 1984
    [13] JOHNSON R H. Integral tests of neutron cross sections for iron, nobium, beryllium, and polyethylene[D]. Urbana, Illinois: University of Illinois at Urbana-Champaign, 1975.
    [14] WILLIAMS M L, ABOUGHANTOUS C, ASGARI M, et al. Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V and ENDF/B-VI iron evaluations[J]. Annals of Nuclear Energy, 1991, 18(10): 549-565. doi: 10.1016/0306-4549(91)90055-3
    [15] DEVKIN B V, KOBOZEV M G, SIMAKOV S P, et al. Neutron leakage spectra from iron spheres[C]//Proceedings of the 18th Symposium on Fusion Technology, 22-26 Aug 1994, Karlsruhe, 1994
    [16] NUNNENMANN E, FISCHER U. V&V analyses of the GEANT4 Monte Carlo code toolkit with computational and experimental fusion neutronics benchmarks[J]. Fusion Engineering and Design, 2019, 146: 1579-1582. doi: 10.1016/j.fusengdes.2019.02.132
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出版历程
  • 收稿日期:  2021-01-04
  • 修回日期:  2021-09-18
  • 刊出日期:  2022-02-01

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