Grain Size Control by Matrix Phase Additives in Nuclear Thermal Propulsion Cermets
Source abstract
Abstract
Refined grain sizes in the metallic phase of a cermet nuclear fuel have been reported to provide improved performance and survivability of the fuel in nuclear thermal propulsion (NTP) applications. In this paper, we study the use of ZrC nanoparticles, which have a low neutron absorption cross-section, as Zener pinning sites for the tungsten matrix in a surrogate fuel - yttria stabilized zirconia (YSZ) – cermet. While the ZrC additions were found to successfully pin grain boundaries, subsequent high temperature hydrogen exposure at 2500 K for 1 hour resulted in significantly more catastrophic cracking in comparison to control specimens with no ZrC additions. This increase in cracking is explained by two gas formation mechanisms - hydrogen recombination at defect sites and water vapor formation from the reduction of YSZ.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. Spark Plasma Sintering of W-UO2 cermets10.1016/j.jnucmat.2012.08.044 ↗
2. Low-enriched cermet-based fuel options for a nuclear thermal propulsion engine10.1016/j.nucengdes.2018.02.036 ↗
3. CERMETS for Use in Nuclear Thermal Propulsion
4. Microstructural evolution of Mo-UO2 cermets under high temperature hydrogen environments10.1016/j.jnucmat.2020.152297 ↗
5. Cermet surrogate nuclear fuels from coated powders10.1016/j.jnucmat.2021.153246 ↗
6. Nuclear Thermal Propulsion (NTP): A Proven Growth Technology for Human NEO /Mars Exploration Missions
7. Stewart · 2015
8. L.L. Lyon, LA-5398-MS, Performance of (U,Zr)C-graphite (composite) and of (U,Zr)C (carbide) fuel elements in the Nuclear Furnace 1 test reactor, 1973.10.2172/4419566 ↗
9. J.M. Taub, LA-5931 A Review of Fuel Element Development for Nuclear Rocket Engines, 1975.
10. C.W. Watson, LA-12784-MS, Nuclear rockets: High-performance propulsion for Mars, 1996.
11. High density, uniformly distributed W/UO2 for use in Nuclear Thermal Propulsion10.1016/j.jnucmat.2017.01.033 ↗
12. Literature review of thermal and radiation performance parameters for high-temperature, uranium dioxide fueled cermet materials10.1016/j.jnucmat.2007.03.024 ↗
13. Spark Plasma Sintering of simulated radioisotope materials within tungsten cermets10.1016/j.jnucmat.2009.05.012 ↗
14. M.W. Barnes, D.S. Tucker, G.C. Marshall, Nuclear Rocket Ceramic Metal Fuel Fabrication Using Tungsten Powder Coating and Spark Plasma Sintering, 2017.
15. Suarez · 2013
16. Field-assisted sintering technology/spark plasma sintering: Mechanisms, materials, and technology developments10.1002/adem.201300409 ↗
17. W.H. Lenz, LA-3329-MS, Improved Performance of W-Based UO2 Fuel Materials, 1965.
18. R.J. Baker, J.L. Daniel, W.J. Lacker, R.J. Lobsinger, F.A. Scott, E.A. Snajdr, W.E. Roake, NASA-CR-54840, Final Report Basic Behavior and Properties of W-UO2 Cermets, 1965.
19. Grain Boundary Migration and Zener Pinning in Particle-Containing Copper Crystals10.1016/1359-6454(95)00421-1 ↗
20. Properties of zirconium carbide for nuclear fuel applications10.1016/j.jnucmat.2013.05.037 ↗
21. Observation of hydrogen trapping at dislocations, grain boundaries, and precipitates10.1126/science.aaz0122 ↗
22. Long-range hydrogen-binding effects of carbide interfaces in iron
23. Hydrogen trapping and storage in the group IVB-VIB transition metal carbides10.1016/j.matdes.2022.110399 ↗
24. Production and hot hydrogen testing of subscale molybdenum cermets for nuclear thermal propulsion
25. Carpenter · 2019
26. Preparation of Hypostoichiometric U02-X at Low Temperatures and Study of Some Properties10.1007/BF02117563 ↗
27. Effect of yttria content on the zirconia unit cell parameters10.1111/j.1551-2916.2011.04862.x ↗
28. Core shell coatings for nuclear thermal propulsion cermets10.1016/j.surfcoat.2022.128661 ↗
29. Benensky · Operational Characterization and Testing of NASA MSFC'S Compact Fuel Element Environmental Test (CFEET) · 2018
30. M.E. Mackay, A. Tuteja, P.M. Duxbury, C.J. Hawker, B.V. Horn, Z. Guan, G. Chen, R.S. Krishnan, General Strategies for Nanoparticle Dispersiong, Science (1979). 311 (2006) 1740–1743. doi:10.1126/science.1118052.10.1126/science.1122225 ↗
31. Carbide nanoparticle dispersion techniques for metal powder metallurgy10.3390/met11060871 ↗
32. The stoichiometry of hydrogen reduced zirconia and its influence on catalytic activity - Part 1: Volumetric and conductivity studies10.1039/b109887j ↗
33. Hydrogen surface reactions and adsorption studied on Y2O 3, YSZ, and ZrO210.1021/jp5008472 ↗
34. The measurement of thermal expansion coefficient of tungsten at elevated temperatures10.1088/0022-3735/2/6/311 ↗
35. Thermal expansion coefficient of yttria stabilized zirconia for various yttria contents10.1016/j.ssi.2004.08.021 ↗
36. Thermal Expansion of Zirconium Carbide at 1200–2850 K10.1134/S0018151X18060159 ↗
37. Hydrogen embrittlement of metals: A primer for the failure analyst10.1007/s11668-008-9133-x ↗
38. Review of Hydrogen Embrittlement in Metals: Hydrogen Diffusion, Hydrogen Characterization, Hydrogen Embrittlement Mechanism and Prevention10.1007/s40195-020-01039-7 ↗
39. Nickel Oxide Reduction by Hydrogen: Kinetics and Structural Transformations10.1021/acs.jpcc.5b04313 ↗
40. J. Chen, P.C. Hayes, Mechanisms and Kinetics of Reduction of Solid NiO in CO/CO2 and CO/Ar Gas Mixtures, Metallurgical and Materials Transactions B: Process Metallurgy and Materials Processing Science. 50 (2019) 2623–2635. doi:10.1007/s11663-019-01662-5.10.1007/s11663-019-01662-5 ↗
41. T.G. Duffin, Corrosion and Microstructural Characterization of Molybdenum-YSZ Cermets Following Hydrogen Exposure up to 2630 K, 2022. https://trace.tennessee.edu/utk_graddiss.10.1016/j.jnucmat.2023.154692 ↗
42. Electrochemical hydrogen storage in Ti-V-based alloys surface-modified with carbon nanoparticles10.1088/0957-4484/17/1/045 ↗
43. Carbon influence on hydrogen absorption and adsorption on Fe-C alloy surfaces10.1016/j.susc.2020.121606 ↗
44. An overview of creep in tungsten and its alloys10.1016/j.ijrmhm.2019.03.022 ↗
45. Meyers · 2009