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Title: Effects of fission yield data in the calculation of antineutrino spectra for U 235 ( n , fission ) at thermal and fast neutron energies

Abstract

Fission yields form an integral part of the prediction of antineutrino spectra generated by nuclear reactors, but little attention has been paid to the quality and reliability of the data used in current calculations. Following a critical review of the thermal and fast ENDF/B-VII.1 235U fission yields, deficiencies are identified and improved yields are obtained, based on corrections of erroneous yields, consistency between decay and fission yield data, and updated isomeric ratios. These corrected yields are used to calculate antineutrino spectra using the summation method. An anomalous value for the thermal fission yield of 86Ge generates an excess of antineutrinos at 5–7 MeV, a feature which is no longer present when the corrected yields are used. Thermal spectra calculated with two distinct fission yield libraries (corrected ENDF/B and JEFF) differ by up to 6% in the 0–7 MeV energy window, allowing for a basic estimate of the uncertainty involved in the fission yield component of summation calculations. Lastly, the fast neutron antineutrino spectrum is calculated, which at the moment can only be obtained with the summation method and may be relevant for short baseline reactor experiments using highly enriched uranium fuel.

Authors:
 [1];  [1];  [1];  [2]
  1. Brookhaven National Lab. (BNL), Upton, NY (United States)
  2. International Atomic Energy Agency, Vienna (Austria)
Publication Date:
Research Org.:
Brookhaven National Lab. (BNL), Upton, NY (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Nuclear Physics (NP) (SC-26)
OSTI Identifier:
1337617
Alternate Identifier(s):
OSTI ID: 1245040
Report Number(s):
BNL-108548-2016-JA
Journal ID: ISSN 0031-9007; PRLTAO; R&D Project: EST-003-NEFA; KB0301041
Grant/Contract Number:  
SC00112704; AC02-98CH10886
Resource Type:
Accepted Manuscript
Journal Name:
Physical Review Letters
Additional Journal Information:
Journal Volume: 116; Journal Issue: 13; Journal ID: ISSN 0031-9007
Publisher:
American Physical Society (APS)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS

Citation Formats

Sonzogni, A. A., McCutchan, E. A., Johnson, T. D., and Dimitriou, P. Effects of fission yield data in the calculation of antineutrino spectra for U235(n,fission) at thermal and fast neutron energies. United States: N. p., 2016. Web. doi:10.1103/PhysRevLett.116.132502.
Sonzogni, A. A., McCutchan, E. A., Johnson, T. D., & Dimitriou, P. Effects of fission yield data in the calculation of antineutrino spectra for U235(n,fission) at thermal and fast neutron energies. United States. doi:10.1103/PhysRevLett.116.132502.
Sonzogni, A. A., McCutchan, E. A., Johnson, T. D., and Dimitriou, P. Fri . "Effects of fission yield data in the calculation of antineutrino spectra for U235(n,fission) at thermal and fast neutron energies". United States. doi:10.1103/PhysRevLett.116.132502. https://www.osti.gov/servlets/purl/1337617.
@article{osti_1337617,
title = {Effects of fission yield data in the calculation of antineutrino spectra for U235(n,fission) at thermal and fast neutron energies},
author = {Sonzogni, A. A. and McCutchan, E. A. and Johnson, T. D. and Dimitriou, P.},
abstractNote = {Fission yields form an integral part of the prediction of antineutrino spectra generated by nuclear reactors, but little attention has been paid to the quality and reliability of the data used in current calculations. Following a critical review of the thermal and fast ENDF/B-VII.1 235U fission yields, deficiencies are identified and improved yields are obtained, based on corrections of erroneous yields, consistency between decay and fission yield data, and updated isomeric ratios. These corrected yields are used to calculate antineutrino spectra using the summation method. An anomalous value for the thermal fission yield of 86Ge generates an excess of antineutrinos at 5–7 MeV, a feature which is no longer present when the corrected yields are used. Thermal spectra calculated with two distinct fission yield libraries (corrected ENDF/B and JEFF) differ by up to 6% in the 0–7 MeV energy window, allowing for a basic estimate of the uncertainty involved in the fission yield component of summation calculations. Lastly, the fast neutron antineutrino spectrum is calculated, which at the moment can only be obtained with the summation method and may be relevant for short baseline reactor experiments using highly enriched uranium fuel.},
doi = {10.1103/PhysRevLett.116.132502},
journal = {Physical Review Letters},
number = 13,
volume = 116,
place = {United States},
year = {2016},
month = {4}
}

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