Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR

Brown, Nicholas R.; Gorton, Jacob P.; Collins, Benjamin S.; Nelson, Andrew T.

doi:10.1016/j.nucengdes.2019.110317

Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR

Journal Article · Sat Aug 31 00:00:00 EDT 2019 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2019.110317· OSTI ID:1661259

^[1]; Gorton, Jacob P. ^[1]; ^[2]; ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The reactor performance and safety characteristics of mixed thorium mononitride (ThN) and uranium mononitride (UN) fuels in a pressurized water reactor (PWR) are investigated to discern the potential nonproliferation, waste, and accident tolerance benefits provided by this fuel form. In this paper, we present results from an initial screening of mixed ThN-UN fuels in normal PWR operating conditions and compares their reactor performance to UO₂ in terms of fuel cycle length, reactivity coefficients, and thermal safety margin. ThN has been shown to have a significantly greater thermal conductivity than UO₂ and UN. Admixture with a UN phase is required because thorium initially contains no fissile isotopes. Results from this study show that ThN-UN mixtures exist that can match the cycle length of a UO₂-fueled reactor by using ²³⁵U enrichments greater than 5% but less than 20% in the UN phase. Reactivity coefficients were calculated for UO₂, UN, and ThN-UN mixtures, and it was found that the fuel temperature and moderator temperature coefficients of the nitride-based fuels fall within the acceptable limits specified by the AP1000 Design Control Document. Reduced soluble boron and control rod worth for these fuel forms indicates that the shutdown margin may not be sufficient, and design changes to the control systems may need to be considered. The neutronic impact of ¹⁵N enrichment on reactivity coefficients is also included. Due to the greatly enhanced thermal conductivity of the nitride-based fuels, the UN and ThN-UN fuels provide additional margin to fuel melting temperature relative to UO₂.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1661259

Alternate ID(s):: OSTI ID: 1776134
OSTI ID: 22893627

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: 1 Vol. 355; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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