ZHONG WENFA;HU YONGMING Institute of Nuclear Energy Technology, Qinghua University, Beijing. CALCULATION OF NEUTRON MICRO CROSS SECTIONS USING UNSOLVED RESONANCE PARAMETERS[J]. Atomic Energy Science and Technology, 1986, 20(3): 371-371. DOI: 10.7538/yzk.1986.20.03.0371
Citation: ZHONG WENFA;HU YONGMING Institute of Nuclear Energy Technology, Qinghua University, Beijing. CALCULATION OF NEUTRON MICRO CROSS SECTIONS USING UNSOLVED RESONANCE PARAMETERS[J]. Atomic Energy Science and Technology, 1986, 20(3): 371-371. DOI: 10.7538/yzk.1986.20.03.0371

CALCULATION OF NEUTRON MICRO CROSS SECTIONS USING UNSOLVED RESONANCE PARAMETERS

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  • Received Date: January 18, 1984
  • A method which calculates neutron scattering, capture and fission crosssection using unsolved resonance parameters in ENDF/B library is given. TheDoppler broadening is considered. The calculations are carried out for ~(235)U,~(238)U and ~(239)Pu in different temperatures and different scattering cross sections.The results are satisfactory.
  • [1]
    Bhat, M. R., BNL-50296, 1971.
    [2]
    Gaber, D. et al., BNL-NCS-50496, 1975.
    [3]
    G. I. 贝尔, S. 格拉斯登著,核反应堆理论,北京,原子能出版社,1979年.
    [4]
    Steen, N. M., Nucl. Sci. Eng., 38, 244 (1975).
    [5]
    Bhat, M. R. and Lee-Whiting,G.E.,Nucl.Instruments and Methods, 47,277(1967).
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