Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors

Iyad Al-Qasir, Victor Gillette, Abdallah Qteish

Research output: Contribution to journalArticlepeer-review

15 Scopus citations

Abstract

The use of uranium mono-nitride (UN) fuel in light water reactors has recently received an increasing interest. Neutronic and thermal-hydraulic performance of UN and associated composite fuels have been studied lately for several types of light water reactors. A comprehensive and detailed analysis of the performance of these reactors using nitride fuels require a complete set of thermal neutron scattering libraries of UN. In this work, the thermal neutron scattering law, the inelastic and coherent elastic scattering cross sections of UN are calculated at different temperatures starting from the phonon density of states obtained from first-principles electronic structure calculations. Excellent agreement between the calculated phonon dispersion relations and the experimental data have been obtained. Due to the huge mass difference between the constituent elements, the calculated nitrogen optic phonon modes are well-separated from those of uranium acoustic phonon modes. The nitrogen scattering law shows a set of well-defined and equally-spaced peaks corresponding to multi-phonon scattering processes, demonstrating that the nitrogen atoms behave as nearly independent three-dimensional quantum harmonic oscillators. The effects of this behavior on the computed inelastic scattering cross sections are thoroughly discussed. As 14N has a large absorption cross section in the thermal energy range and results in a production of 14C, the scattering law and the inelastic scattering cross section of U15N are also calculated. Our calculated scattering cross sections are discussed in comparison with the ENDF/B-VIII.0 thermal neutron scattering cross sections of UN and UO2, and it has been found that U15N fuel can be a viable alternative to the UO2 one.

Original languageEnglish
Pages (from-to)68-78
Number of pages11
JournalAnnals of Nuclear Energy
Volume127
DOIs
StatePublished - May 2019
Externally publishedYes

Funding

We would like to thank Mrs. Naila Perveen from Center for Advanced Materials Research at the University of Sharjah for helping in data manipulation. We would like to express our gratitude to Dr. J.I. Marquez, from Centro Atomico Bariloche, for useful discussion. This work was supported by the University of Sharjah, under grant No. 140446.

Keywords

  • Advanced tolerant fuel
  • ENDF/B-VIII
  • First-principles calculations
  • Light water reactors
  • Phonons
  • Scattering cross sections
  • Thermal neutrons
  • Uranium mono-nitride

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