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

2015/12/23 by X. B., Ma, X. B., Yushan Zhao +7 · 1 citation
Engineering · Physics and Astronomy · #FOS: Physical sciences #High Energy Physics - Experiment (hep-ex) #Instrumentation and Detectors (physics.ins-det) #Neutrino Physics Research #Nuclear Experiment (nucl-ex) #Nuclear reactor physics and engineering #Scientific Research and Discoveries

paper · pdf · doi:10.48550/arxiv.1512.07353

openalex publication_date 2015/12/23 · openalex created_date 2019/06/27 · openalex updated_date 2026/07/28

Abstract

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 spent fuel, many data are 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 the isotopes in the spend fuel. A method to calculate the contribution of SNF is proposed in this study. In this method, reactor simulation code verified by experiment have been used to simulate the fuel depletion by taking into account more than 2000 isotopes and fission products, the quantity of SNF in each six spend fuel pool, and the antineutrino spectrum of SNF varying with time after SNF discharged from core. Results show that the contribution of SNF to the total antineutrino flux is about 0.26%~0.34%, and the shutdown impact is about 20%. The SNF spectrum would distort the softer part of antineutrino spectra, and the maximum contribution from SNF is about 3.0%, but there is 18% difference between line evaluate method and under evaluate method. In addition, non-equilibrium effects are also discussed, and the results are compatible with theirs considering the uncertainties.

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