activity
20142026
most citedA new MC-based method to evaluate the fission fraction uncertainty at reactor neutrino experiment

3 citations · 6 across the 6 of their papers we have counts for

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Showing 2015 · physics.ins-detShow all

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physics.ins-det2015

Antineutrino flux and spectrum calculation for spent nuclear fuel for the Daya Bay antineutrino experiment

X. B. Ma, Y. F. Zhao, Y. X. Chen +2

Spent nuclear fuel (SNF) antineutrino flux is an important source of uncertainties for a reactor neutrino flux prediction. However, if one want to determine the contribution of spe…