Cumulative fission yield measurements with 14.7 MeV neutrons on 238U*

被引:2
|
作者
Yang, Xianlin [1 ]
Lan, Changlin [1 ]
Nie, Yangbo [2 ]
Jiang, Liyang [2 ]
Qiu, Yijia [1 ]
Ge, Yujie [1 ]
Chen, Hongtao [2 ]
Zhang, Kai [2 ]
Wei, Yuting [1 ]
Wang, Jiahao [1 ]
Jiang, Gong [1 ]
Ruan, Xichao [2 ]
Yang, Yi [2 ]
机构
[1] Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China
[2] China Inst Atom Energy, Key Lab Nucl Data, Beijing 102413, Peoples R China
基金
中国国家自然科学基金;
关键词
U-238; fission yields; DT neutron source; activation method; PRODUCT YIELDS; THERMAL-NEUTRONS; U-238; ENERGIES; SPECTRUM; PU-239;
D O I
10.1088/1674-1137/aca1ab
中图分类号
O57 [原子核物理学、高能物理学];
学科分类号
070202 ;
摘要
The fission yield data in the 14 MeV energy neutron induced fission of U-238 play an important role in decay heat calculations and generation-IV reactor designs. In order to accurately measure fission product yields (FPYs) of U-238 induced by 14 MeV neutrons, the cumulative yields of fission products ranging from Sr-92 to Nd-147 in the U-238(n, f) reaction with a 14.7 MeV neutron were determined using an off-line gamma-ray spectrometric technique. The 14.7 MeV quasi-monoenergetic neutron beam was provided by the K-400 D-T neutron generator at China Academy of Engineering Physics (CAEP). Fission products were measured by a low background high purity germanium gamma spectrometer. The neutron flux was obtained from the Nb-93 (n, 2n)Nb-92m reaction, and the mean neutron energy was calculated using the cross-section ratios for the Zr-90(n, 2n)Zr-89 and Nb-93(n, 2n)Nb-92m reactions. With a series of corrections, high precision cumulative yields of 20 fission products were obtained. Our FPYs for the U-238(n, f) reaction at 14.7 MeV were compared with the existing experimental nuclear reaction data and evaluated nuclear data, respectively. The results will be helpful in the design of a generation-IV reactor and the construction of evaluated fission yield databases.
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页数:7
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