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Title: Uranium nitride tristructural-isotropic fuel particle

Abstract

A summary of activities around concept development, design, manufacturing, and early irradiation testing of a novel coated fuel particle, uranium nitride tristructural-isotropic fuel is provided. This fuel particle offers significantly higher uranium density over historic manifestations of coated fuel particles and may be more optimal for a range of advanced reactor applications. After reviewing the design process, steps involving production of this fuel form are discussed. Low burnup irradiation data on this fuel particle are now available, indicating that performance metrics have been met to date based on the original design expectations.

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1606770
Alternate Identifier(s):
OSTI ID: 1598380
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 531; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Terrani, Kurt, Jolly, Brian C., and Harp, Jason. Uranium nitride tristructural-isotropic fuel particle. United States: N. p., 2020. Web. doi:10.1016/j.jnucmat.2020.152034.
Terrani, Kurt, Jolly, Brian C., & Harp, Jason. Uranium nitride tristructural-isotropic fuel particle. United States. https://doi.org/10.1016/j.jnucmat.2020.152034
Terrani, Kurt, Jolly, Brian C., and Harp, Jason. Tue . "Uranium nitride tristructural-isotropic fuel particle". United States. https://doi.org/10.1016/j.jnucmat.2020.152034. https://www.osti.gov/servlets/purl/1606770.
@article{osti_1606770,
title = {Uranium nitride tristructural-isotropic fuel particle},
author = {Terrani, Kurt and Jolly, Brian C. and Harp, Jason},
abstractNote = {A summary of activities around concept development, design, manufacturing, and early irradiation testing of a novel coated fuel particle, uranium nitride tristructural-isotropic fuel is provided. This fuel particle offers significantly higher uranium density over historic manifestations of coated fuel particles and may be more optimal for a range of advanced reactor applications. After reviewing the design process, steps involving production of this fuel form are discussed. Low burnup irradiation data on this fuel particle are now available, indicating that performance metrics have been met to date based on the original design expectations.},
doi = {10.1016/j.jnucmat.2020.152034},
url = {https://www.osti.gov/biblio/1606770}, journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = C,
volume = 531,
place = {United States},
year = {2020},
month = {2}
}

Journal Article:

Citation Metrics:
Cited by: 1 work
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