Zirconium carbonitride pellets by internal sol gel and spark plasma sintering as inert matrix fuel material
Source abstract
Abstract
Inert matrix fuel is a fuel type where the fissile material is blended with a solid diluent material. In this work zirconium carbonitride microspheres have been produced by internal sol gel technique, followed by carbothermal reduction. Material nitride purities in the produced materials ranged from Zr(N0.45C0.55) to Zr(N0.74C0.26) as determined by X-ray diffraction and application of Vegard's law. The zirconium carbonitride microspheres have been pelletized by spark plasma sintering (SPS) and by conventional cold pressing and sintering. In all SPS experiments cohesive pellets were formed. Maximum final density reached by SPS at 1700 C was 87% theoretical density (TD) compared to 53% TD in conventional sintering at 1700 C. Pore sizes in all the produced pellets were in the mm scale and no density gradients could be observed by computer tomography.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (21)
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1. Selection of materials as diluents for burning of plutonium fuels in nuclear reactors10.1016/S0022-3115(99)00144-0 ↗
2. Popov · 2000
3. The effect of plutonium content on the thermal conductivity of (U, Pu)O2 solid solutions10.1016/0022-3115(71)90040-7 ↗
4. Thermal conductivity of actinide mononitride solid solutions10.1016/S0925-8388(98)00168-6 ↗
5. The decomposition pressure and melting point of uranium mononitride10.1021/j100798a525 ↗
6. The chemical thermodynamic properties of plutonium compounds10.1021/cr60247a002 ↗
7. Zur Mischallkristallbildung in den quasibinären Systemen von UN und den Mononitriden der IV A-Gruppe TiN, ZrN und HfN10.1007/BF00913744 ↗
8. Zirconium nitride as inert matrix for fast systems10.1016/S0022-3115(03)00133-8 ↗
9. Preparation of high density uranium nitride and uranium carbonitride fuel pellets10.1080/18811248.1972.9734891 ↗
10. Mechanically induced gas – solid reaction for the synthesis of nanocrystalline ZrN powders and their subsequent consolidations10.1016/S0925-8388(00)01175-0 ↗
11. Advanced fuel fabrication10.1016/0022-3115(89)90182-7 ↗
12. The KEMA U(VI)-process for the production of UO2 microspheres
13. A U(VI) – process for microsphere production
14. A study of chemical parameters of the internal gelation based Sol-Gel process for uranium dioxide10.1016/0022-3115(87)90026-2 ↗
15. The basic chemistry involved in the internal-gelation method of precipitating uranium as determined by pH measurements10.1524/ract.1987.42.3.121 ↗
16. Preparation of yttria-stabilized zirconia-ceria kernels as fuel precursors using internal gelation10.1524/ract.2008.1489 ↗
17. Structure of the hydrated, hydrolysed, and solvated zirconium (IV) and hafnium (IV) ions in water and aprotic oxygen donor solvents. A crystallographic, EXAFS spectroscopic and large angle X-ray scattering study10.1039/B402804J ↗
18. Low-temperature hydrothermal synthesis of yttrium-doped zirconia powders10.1111/j.1151-2916.1999.tb01891.x ↗
19. Diffractométrie de Rayons X à haute temperature et réactivité chimique: application à la nitruration carbothermique de la zircone10.1016/0022-5088(91)90078-I ↗
20. Density gradients in ceramic pellets measured by computed tomography10.1016/0168-9002(88)90997-7 ↗
21. Measuring physical density with X-ray computed tomography10.1016/S0963-8695(97)00020-0 ↗