Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln

Benson, Michael T.; Yao, Tainkai; Teng, Fei; Wang, Yachun; King, James A.; Zhang, Jinsuo

doi:10.1016/j.jnucmat.2023.154729

Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln

Journal Article · Sat Sep 09 00:00:00 EDT 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154729· OSTI ID:2283354

^[1]; ^[1]; ^[1]; ^[1]; ^[1]; Zhang, Jinsuo ^[2]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)

Antimony is being investigated as a potential additive to metallic fuel to control fuel-cladding chemical interactions (FCCI). The most detrimental elements involved in FCCI are fission product lanthanides, leading to brittle intermetallics and low melting eutectic phases. Previous investigations of Sb as an additive focused on U-10Zr, in wt. %, as the fuel. The current investigation expands that to include Pu in the fuel. Here, two alloys, U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln (wt. %, Ln=53Nd-25Ce-16Pr-6La) have been investigated using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) to characterize the fuel as-cast microstructure and the microstructure after introduction of lanthanides. Sb reacts with Zr initially, forming Zr₂Sb and Zr₅Sb₃, with as much as 20 at. % interstitial Pu present. In the presence of lanthanides, Sb forms Ln₄Sb₃ with the lanthanides, containing ~14 at. % Pu. The Pu is substitutional for the lanthanides in the crystal lattice.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2283354

Alternate ID(s):: OSTI ID: 2368887

Report Number(s):: INL/JOU-23-72309-Revision-0

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 587; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (31)

Swelling behavior of U-Pu-Zr fuel Hofman, Gerard L.; Pahl, R. G.; Lahm, C. E. Metallurgical Transactions A, Vol. 21, Issue 2 https://doi.org/10.1007/BF02671924	journal	February 1990
Effect of Zr thin film on Zr foil as a FCCI barrier between lanthanide (La-Ce) and clad material Lee, Kang Soo; Kim, In Yea; Lee, Wooyoung Metals and Materials International, Vol. 21, Issue 3 https://doi.org/10.1007/s12540-015-4433-7	journal	May 2015
A synthetic and structural study of the zirconium-antimony system Garcia, Eduardo; Corbett, John D. Journal of Solid State Chemistry, Vol. 73, Issue 2 https://doi.org/10.1016/0022-4596(88)90130-2	journal	April 1988
Neutron powder diffraction and inelastic scattering study of the structures of Zr2Pd, Zr2PdD1.70 and Zr2PdD1.96 Maeland, A. J.; Lukacevic, E.; Rush, J. J. Journal of the Less Common Metals, Vol. 129 https://doi.org/10.1016/0022-5088(87)90035-X	journal	February 1987
Metallic fast reactor fuels Hofman, G. L.; Walters, L. C.; Bauer, T. H. Progress in Nuclear Energy, Vol. 31, Issue 1-2 https://doi.org/10.1016/0149-1970(96)00005-4	journal	January 1997
Fuels for sodium-cooled fast reactors: US perspective Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.010	journal	September 2007
Metallic fuels for advanced reactors Carmack, W. J.; Porter, D. L.; Chang, Y. I. Journal of Nuclear Materials, Vol. 392, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.03.007	journal	July 2009
Lanthanides in metallic nuclear fuels: Their behavior and methods for their control Mariani, R. D.; Porter, D. L.; O’Holleran, T. P. Journal of Nuclear Materials, Vol. 419, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.08.036	journal	December 2011
Coexistence of the α and δ phases in an as-cast uranium-rich U–Zr alloy McKeown, J. T.; Irukuvarghula, S.; Ahn, S. Journal of Nuclear Materials, Vol. 436, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.313	journal	May 2013
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins Carmack, W. J.; Chichester, H. M.; Porter, D. L. Journal of Nuclear Materials, Vol. 473 https://doi.org/10.1016/j.jnucmat.2016.02.019	journal	May 2016
Effect of indium addition in U-Zr metallic fuel on lanthanide migration Kim, Yeon Soo; Wiencek, T.; O'Hare, E. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.11.012	journal	February 2017
SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln Benson, Michael T.; King, James A.; Mariani, Robert D. Journal of Nuclear Materials, Vol. 494 https://doi.org/10.1016/j.jnucmat.2017.07.057	journal	October 2017
Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides Xie, Yi; Benson, Michael T.; King, James A. Journal of Nuclear Materials, Vol. 498 https://doi.org/10.1016/j.jnucmat.2017.10.039	journal	January 2018
Thermodynamic stability studies of Ce-Sb compounds with Fe Xie, Yi; Zhang, Jinsuo; Benson, Michael T. Journal of Nuclear Materials, Vol. 499 https://doi.org/10.1016/j.jnucmat.2017.12.008	journal	February 2018
Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive Benson, Michael T.; He, Lingfeng; King, James A. Journal of Nuclear Materials, Vol. 502 https://doi.org/10.1016/j.jnucmat.2018.02.012	journal	April 2018
Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln Benson, Michael T.; He, Lingfeng; King, James A. Journal of Nuclear Materials, Vol. 508 https://doi.org/10.1016/j.jnucmat.2018.05.062	journal	September 2018
Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations Harp, Jason M.; Chichester, Heather J. M.; Capriotti, Luca Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.003	journal	October 2018
Postirradiation examination on metallic fuel in the AFC-2 irradiation test series Harp, Jason M.; Capriotti, Luca; Chichester, Heather J. M. Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.019	journal	October 2018
Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln Benson, Michael T.; Xie, Yi; He, Lingfeng Journal of Nuclear Materials, Vol. 518 https://doi.org/10.1016/j.jnucmat.2019.03.014	journal	May 2019
Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with added minor actinides Wright, Karen E.; Harp, Jason M.; Capriotti, Luca Journal of Nuclear Materials, Vol. 526 https://doi.org/10.1016/j.jnucmat.2019.151745	journal	December 2019
Postirradiation characterization of palladium as an additive for fuel cladding chemical interaction mitigation in metallic fuel Di Lemma, Fidelma G.; Trowbridge, Tammy M.; Capriotti, Luca Journal of Nuclear Materials, Vol. 558 https://doi.org/10.1016/j.jnucmat.2021.153403	journal	January 2022
Direct and pulse electroplating effects on the diffusion barrier property of plasma-nitrided Cr coatings on HT9 steel Yeo, Sunghwan; Yun, Hee Soo; Kim, Jun Hwan Journal of Nuclear Materials, Vol. 574 https://doi.org/10.1016/j.jnucmat.2022.154218	journal	February 2023
Efficient computational search for lanthanide-binding additive dopants for advanced U-Zr based fuels Jiang, Chao; Xie, Yi; Benson, Michael T. Materialia, Vol. 10 https://doi.org/10.1016/j.mtla.2020.100653	journal	May 2020
FAST irradiations and initial post irradiation examinations – Part I Beausoleil, G.; Capriotti, L.; Curnutt, B. Nuclear Engineering and Technology, Vol. 54, Issue 11 https://doi.org/10.1016/j.net.2022.07.008	journal	November 2022
Lanthanide migration and immobilization in metallic fuels Xie, Yi; Zhang, Jinsuo; Li, Xiang Progress in Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.pnucene.2018.08.019	journal	November 2018
Metallic Fuels: The EBR-II Legacy and Recent Advances Mariani, Robert D.; Porter, Douglas L.; Hayes, Steven L. Procedia Chemistry, Vol. 7 https://doi.org/10.1016/j.proche.2012.10.078	journal	January 2012
Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review Matthews, Christopher; Unal, Cetin; Galloway, Jack Nuclear Technology, Vol. 198, Issue 3 https://doi.org/10.1080/00295450.2017.1323535	journal	June 2017
Fuel Performance Design Basis for the Versatile Test Reactor Porter, D. L.; Crawford, D. C. Nuclear Science and Engineering, Vol. 196, Issue sup1 https://doi.org/10.1080/00295639.2021.2009983	journal	January 2022
Amorphous phase formation in irradiated intermetallic compounds Brimhall, J. L.; Kissinger, H. E.; Charlot, L. A. Radiation Effects, Vol. 77, Issue 3-4 https://doi.org/10.1080/00337578308228192	journal	January 1983
Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel Via Electrolytic Reduction and Electrorefining Herrmann, S. D.; Li, S. X. Nuclear Technology, Vol. 171, Issue 3 https://doi.org/10.13182/NT171-247	journal	September 2010
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard Nuclear Technology, Vol. 65, Issue 2 https://doi.org/10.13182/NT84-A33408	journal	May 1984

Similar Records

Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln

Journal Article · Thu Mar 14 20:00:00 EDT 2019 · Journal of Nuclear Materials · OSTI ID:1511488

Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln

Journal Article · Mon May 28 20:00:00 EDT 2018 · Journal of Nuclear Materials · OSTI ID:1478245

Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides

Journal Article · Thu Aug 09 20:00:00 EDT 2018 · Journal of Nuclear Materials · OSTI ID:1465695

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
U-Zr fuel
fuel additive
fuel-cladding chemical interaction
lanthanide
lanthanides
metallic fuel

Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln

Citation Formats

References (31)

Similar Records

Related Subjects