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Antineutrino flux and spectrum calculation for spent nuclear fuel for the daya bay antineutrino experiment
Ma, X. B.1; Zhao, Y. F.1; Chen, Y. X.1; Zhong, W. L.2; An, F. P.3
刊名Nuclear physics a
2017-10-01
卷号966页码:294-305
关键词Reactor neutrino experiment Uncertainties analysis Spent fuel
ISSN号0375-9474
DOI10.1016/j.nuclphysa.2017.06.009
通讯作者Ma, x. b.(maxb@ncepu.edu.cn)
英文摘要The antineutrino flux from spent nuclear fuel (snf) is an important source of uncertainty when making estimates of a reactor neutrino flux. however, to determine the contribution from snf, sufficient data is needed such as the amount of spent fuel in the pool, the time after discharged from the reactor core, the burnup of each assembly, and the antineutrino spectrum of each isotope in the snf. a method to calculate this contribution is proposed. a reactor simulation code verified against experimental data has been used to simulate fuel depletion by taking into account more than 2000 isotopes and fission products, the quantity of snf in each of the six spent fuel pools, and the time variation of the antineutrino spectra after snf discharging from the core. results show that the snf contribution to the total antineutrino flux is about 0.26%-0.34%, and the shutdown impact is about 20%. the snf spectrum alters the softer part of the antineutrino spectra, and the maximum contribution from the snf is about 3.0%. nevertheless, there is an 18% difference between the line evaluate method and under evaluate method. in addition, non-equilibrium effects are also discussed, and the results are compatible considering the uncertainties. (c) 2017 elsevier b.v. all rights reserved.
WOS关键词THETA(13)
WOS研究方向Physics
WOS类目Physics, Nuclear
语种英语
出版者ELSEVIER SCIENCE BV
WOS记录号WOS:000411536200019
内容类型期刊论文
URI标识http://www.corc.org.cn/handle/1471x/2177098
专题高能物理研究所
通讯作者Ma, X. B.
作者单位1.North China Elect Power Univ, Beijing 102206, Peoples R China
2.Chinese Acad Sci, Inst High Energy Phys, Beijing 100049, Peoples R China
3.East China Univ Sci & Technol, Shanghai, Peoples R China
推荐引用方式
GB/T 7714
Ma, X. B.,Zhao, Y. F.,Chen, Y. X.,et al. Antineutrino flux and spectrum calculation for spent nuclear fuel for the daya bay antineutrino experiment[J]. Nuclear physics a,2017,966:294-305.
APA Ma, X. B.,Zhao, Y. F.,Chen, Y. X.,Zhong, W. L.,&An, F. P..(2017).Antineutrino flux and spectrum calculation for spent nuclear fuel for the daya bay antineutrino experiment.Nuclear physics a,966,294-305.
MLA Ma, X. B.,et al."Antineutrino flux and spectrum calculation for spent nuclear fuel for the daya bay antineutrino experiment".Nuclear physics a 966(2017):294-305.
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