Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering
Source abstract
Abstract
Abstract Thermal conductivity of spark plasma sintered UN/Gd2O3 and UN/GdN composite pellets with various compositions of Gd2O3 (5.0 to 15.0 wt%) and GdN (3.5 to 38.4 wt%) was measured from 25 °C to 1000 °C using laser flash analyzer (LFA). Overall thermal conductivity of both composite pellets decreases with increasing Gd compositions for the entire temperature range measured. The UN/GdN pellets sintered at high temperature (2000 °C) contained solid-solution (U1-x,Gdx)N phase and exhibited 20–65 % higher thermal conductivity than the UN/Gd2O3 pellets. We also confirmed a two-phase structure in low temperature (1800 °C) sintered UN/GdN pellets, which exhibited 14–25 % higher thermal conductivity than solid-solution UN/GdN pellets. This result may indicate that relatively higher thermal conductivity of UN/GdN composite as burnable absorber fuel could be further enhanced with an optimized microstructure.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (34)
Show source-provided references
1. Material property correlations for uranium mononitride. III. Transport properties10.1016/0022-3115(90)90376-X ↗
2. 1966 · 80
3. Thermal conductivity measurements on UO2+x from 300 to 1,400 K10.1080/18811248.1996.9731970 ↗
4. Results of investigations of BREST-type reactor fuel rods with mixed uranium-plutonium nitride fuel, irradiated in BOR-60 and BN-60010.1007/s10512-019-00487-4 ↗
5. Program and results of reactor tests of mixed nitride fuel for fast reactors10.1007/s10512-015-9962-0 ↗
6. Mononitride fuel for fast reactors10.1023/B:ATEN.0000007886.86817.32 ↗
7. Investigations of mixed uranium-plutonium nitride fuel in project breakthrough10.1007/s10512-017-0254-8 ↗
8. Results of studies of BN-600 fuel rods with mixed uranium-plutonium nitride fuel and ChS68-ID c.d. steel cladding10.1007/s10512-019-00534-0 ↗
9. Comparative analyses of coated and composite UN fuel–Monte Carlo based full core LWR study10.1016/j.pnucene.2016.08.014 ↗
10. The Manufacturing of Uranium Nitride for Possible use in Light Water Reactors
11. G. Giudicelli, “Achievable power uprates in pressurized water reactors using uranium nitride fuel by,” 2017.
12. Improved hydrothermal corrosion resistance of un fuel forms via addition of metallic Constituents
13. UN microspheres embedded in UO2 matrix: an innovative accident tolerant fuel10.1016/j.jnucmat.2020.152355 ↗
14. Degradation of UN and UN–U3Si2 pellets in steam environment10.1080/00223131.2016.1274689 ↗
15. Westinghouse AP1000 advanced passive plant
16. The effect of gadolinium content on the thermal conductivity of near-stoichiometric (U,Gd)O2 solid solutions10.1016/0022-3115(82)90375-0 ↗
17. Effect of burn-up on the thermal conductivity of uranium-gadolinium dioxide up to 100 GWd/tHM10.1016/j.jnucmat.2014.07.006 ↗
18. ASTM, “B962-13: standard test methods for density of compacted or sintered powder metallurgy (PM) products using Archimedes’ Principle,” 2013.
19. ASTM, “E1461–07: standard test method for thermal diffusivity by the flash method,” 2012.
20. Flash method of determining thermal diffusivity10.1063/1.1728417 ↗
21. J. Zajas and P. Heiselberg, “Measurements of thermal diffusivity, specific heat capacity and thermal conductivity with LFA 447 apparatus,” 2013.
22. E.O. Speidel and D.L. Keller, “Fabrication and properties of hot-pressed uranium mononitride,” p. 66, 1963.10.2172/4674236 ↗
23. Sintering of UN as a function of temperature and N2 pressure10.1111/j.1151-2916.1971.tb12306.x ↗
24. Wyckoff · 1965
25. S.L. Hayes, J.K. Thomas and K.L. Peddicord, “Material property correlations for uranium mononitride IV. Thermodynamic properties,” vol. 171, pp. 300–318, 1990.10.1016/0022-3115(90)90377-Y ↗
26. Pankratz · 1982
27. An equation for the representation of high-temperature heat content data10.1021/ja01347a029 ↗
28. Thermodynamics of rare earth sesquioxides10.1016/j.pmatsci.2006.09.002 ↗
29. U. Benedict, “The solubility of solid fission products in carbides and nitrides of uranium and plutonium part II: solubility rules based on lattice paramter differences,” vol. EUR-5766, pp. 311–330, 1977.
30. U. Benedict, “The solubility of solid fission products in carbides and nitrides of uranium and plutonium part I: literature review on experimental results,” vol. EUR-5766, 1977.
31. Zur mischkristallbildung von un mit den nitriden der seltenen erden CeN und NdN10.1016/0022-3115(68)90061-5 ↗
32. Zur mischphasenbildung der mononitride in den systemen U- (Y, La, Pr)-N10.1016/0022-3115(69)90077-4 ↗
33. Maxwell · 1873
34. First principles investigation of thermal transport of uranium mononitride10.1016/j.jpcs.2020.109636 ↗