Oxidation and hydrolysis of thorium doped uranium nitride fuel for use in LWR
Source abstract
Abstract
Uranium nitride is being investigated as a replacement for UO2 as it shows enhanced thermal properties and seems to be a promising accident tolerant fuel (ATF) candidate. The main drawback of UN fuel is its innate low oxidation resistance in air/water environments. This becomes a challenge for the implementation of UN fuel in water-cooled reactors. The effect of thorium doping in the stability of uranium nitride microspheres and pellets sintered by spark plasma sintering (SPS) was investigated in oxidizing environments using thermogravimetric analysis and autoclave testing. It was found that during oxidation in air the density had a noticeable effect, increasing the reaction onset temperatures in pellets with higher densities. In addition, thorium doping improved the oxidation resistance of pellets in air by increasing the maximal reaction rate temperature by approximately 50 K. However, this effect was almost nonexistent in highly porous doped microspheres. The interaction with water at 373 K showed that pellets manufactured using SPS can survive unchanged for at least six hours in boiling water, which is an improvement to cold-pressed pellets. At 473 and 573 K, the pellets were oxidized and disintegration into an oxide powder was observed. Thorium-doped uranium nitride pellets did not present any improvement with respect to the oxidation resistance of UN in water at these temperatures.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (22)
Show source-provided references
1. 2016
2. Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design10.1016/j.nucengdes.2016.09.009 ↗
3. FISSION GAS RELEASE OF URANIUM-PLUTONIUM MIXED NITRIDE AND CARBIDE FUELS XA9745729
4. Nitride fuel for Gen IV nuclear power systems10.1007/s10967-018-6316-0 ↗
5. Uranium nitride fuels in superheated steam10.1080/00223131.2017.1291372 ↗
6. Synthesis and sintering of UN-UO2fuel composites10.1016/j.jnucmat.2015.06.029 ↗
7. Lahoda · 2013
8. Lessing · 2012
9. UN microspheres embedded in UO2 matrix: An innovative accident tolerant fuel10.1016/j.jnucmat.2020.152355 ↗
10. A Uranium Nitride Doped with Chromium
11. Kinetic and thermodynamic studies of the dissolution of thoria-urania solid solutions10.1016/j.jnucmat.2004.05.017 ↗
12. Aqueous Dissolution of Urania-Thoria Nuclear Fuel10.13182/NT04-A3522 ↗
13. Dell · 1966
14. Oxidation and hydrolysis kinetic studies on UN10.1016/0022-3115(91)90340-D ↗
15. The ignition of uranium mononitride and uranium monocarbide in oxygen10.1016/0022-3115(67)90185-7 ↗
16. Hydrolysis of Thorium Nitrides and Carbonitrides10.1080/18811248.1971.9733010 ↗
17. Hydrolysis of uranium mononitride10.1039/tf9676301286 ↗
18. Application of SPS in the fabrication of UN and (U,Th)N pellets from microspheres10.1016/j.jnucmat.2020.152181 ↗
19. Oxidation of uranium mononitride10.1016/0022-3115(75)90208-1 ↗
20. Oxidation of accident tolerant fuel candidates
21. Thermodynamic study of solid solutions of uranium oxide. I. Uranium oxide-thorium oxide10.1021/j100876a020 ↗
22. Oxidation Studies of Urania-Thoria Solid Solutions10.1111/j.1151-2916.1960.tb13607.x ↗