IP Library Granted Patent US 12,280,542
Granted Patent B2
US 12,280,542 · App. 18/234,492 · Granted Apr 22, 2025

Photon propagation modified additive manufacturing compositions and methods of additive manufacturing using same

Inventors: John R. Salasin (Lynchburg, VA); Benjamin D. Fisher (Lynchburg, VA)
Assignee: BWXT Advanced Technologies LLC
B29C64/165B33Y10/00B33Y70/10B33Y80/00C08F2/08C08F2/46C08F22/1006C08K3/08C08K3/22G21C3/50C08K2003/0856C08K2201/003
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Quick Facts
Patent No.
US 12,280,542
App. No.
18/234,492
Granted
Apr 22, 2025
Kind
B2
Abstract

Additive manufacturing compositions include low-absorbing particles or non-absorbing particles that have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater than 0 Au and is less 1.0 Au, such as 0.001 Au absorbance≤0.7 Au. Slurries including such particles and an uranium-containing particle and that are used in additive manufacturing processes have an increased penetration depth for curative radiation. Removal of low-absorbing particles or non-absorbing particles during post-processing of as-manufactured products results in pores that create porosity in the as-manufactured product that provide a volume accommodating fission gases and/or can enhance wicking of certain heat pipe coolant liquids. Low-absorbing particles or non-absorbing particles can be functionalized for improved properties, for example, with fissionable material for improved ceramic yields, with burnable poisons or stabilizers for increased homogeneity, with stabilizers for localized delivery of the stabilizer, or with combinations thereof.

Claims (80)

1. A method for manufacturing a component of a nuclear reactor system, the method comprising:

using an additive manufacturing protocol with a nuclear fuel slurry to manufacture a green body of a component of a nuclear reactor system; and

sintering the green body to form the component of the nuclear reactor system,

wherein the nuclear fuel slurry has a composition including (in vol. % relative to total volume of the slurry):

a plurality of first particles

30 vol. % to 40 vol. %;

a plurality of second particles

10 vol. % to 20 vol. %;

at least one monomer resin

25 vol. % to <45 vol. %;

a dispersant

>0 vol. % to 5 vol. %;

a photoabsorber

greater than 0 vol. %; and

a photoinitiator

greater than 0 vol. %,

wherein a total amount of the plurality of first particles and the plurality of second particles is maximum 60 vol. %,

wherein the first particles have a composition including a uranium metal, a uranium metal alloy, a uranium ceramic, or a uranium-molybdenum alloy,

wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater than 0.001 Au and is less 0.7 Au, and

wherein the photoabsorber and photoinitiator operate within an incident wavelength of 300 nm to 700 nm.

2. A method for manufacturing a component of a nuclear reactor system, the method comprising:

using an additive manufacturing protocol with a nuclear fuel slurry to manufacture a green body of a component of a nuclear reactor system,

wherein the nuclear fuel slurry has a composition including (in vol. % relative to total volume of the slurry):

a plurality of first particles

30 vol. % to 40 vol. %;

a plurality of second particles

10 vol. % to 20 vol. %;

at least one monomer resin

25 vol. % to <45 vol. %;

a dispersant

>0 vol. % to 5 vol. %;

a photoabsorber

greater than 0 vol. %; and

a photoinitiator

greater than 0 vol. %,

wherein a total amount of the plurality of first particles and the plurality of second particles is maximum 60 vol. %,

wherein the first particles have a composition including a uranium oxide, a uranium dioxide, a uranium carbide, a uranium oxycarbide, a uranium nitride, a uranium silicide, a uranium fluoride, a uranium chloride, a cermet of uranium oxide and tungsten, a cermet of uranium dioxide and tungsten, a cermet of uranium oxide and molybdenum or a cermet of uranium dioxide and molybdenum,

wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater than 0.001 Au and is less 0.7 Au, and

wherein the photoabsorber and photoinitiator operate within an incident wavelength of 300 nm to 700 nm.

3. The method according to claim 2 , further comprising sintering the green body to form the component of the nuclear reactor system.

4. A method for manufacturing a component of a nuclear reactor system, the method comprising:

using an additive manufacturing protocol with a nuclear fuel slurry to manufacture a green body of a component of a nuclear reactor system,

wherein the nuclear fuel slurry has a composition including (in vol. % relative to total volume of the slurry):

a plurality of first particles

30 vol. % to 40 vol. %;

a plurality of second particles

10 vol. % to 20 vol. %;

at least one monomer resin

25 vol. % to <45 vol. %;

a dispersant

>0 vol. % to 5 vol. %;

a photoabsorber

greater than 0 vol. %; and

a photoinitiator

greater than 0 vol. %,

wherein a total amount of the plurality of first particles and the plurality of second particles is maximum 60 vol. %.

wherein the first particles have a composition including a uranium oxide or a uranium dioxide,

wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater 0.001 Au and is less 0.7 Au, and

wherein the photoabsorber, and photoinitiator operate within an incident wavelength of 300 nm to 700 nm.

5. The method according to claim 4 , further comprising sintering the green body to form the component of the nuclear reactor system.

6. A method for manufacturing a component of a nuclear reactor system, the method comprising:

using an additive manufacturing protocol with a nuclear fuel slurry to manufacture a green body of a component of a nuclear reactor system,

wherein the nuclear fuel slurry has a composition including (in vol. % relative to total volume of the slurry):

a plurality of first particles

30 vol. % to 40 vol. %;

a plurality of second particles

10 vol. % to 20 vol. %;

at least one monomer resin

25 vol. % to <45 vol. %;

a dispersant

>0 vol. % to 5 vol. %;

a photoabsorber

greater than 0 vol. %;

a photoinitiator

greater than 0 vol. %,

wherein a total amount of the plurality of first particles and the plurality of second particles is maximum 60 vol. %,

wherein the first particles have a composition including a uranium-containing material, where the uranium-containing material is U (C, O, N, Si, F, Cl),

wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm that is equal to or greater 0.001 Au and is less 0.7 Au, and

wherein the photoabsorber, and photoinitiator operate within an incident wavelength of 300 nm to 700 nm.

7. The method according to claim 6 , further comprising sintering the green body to form the component of the nuclear reactor system.

Assignments (1)
SECURITY INTEREST Recorded Nov 10, 2025
From: BWXT ADVANCED TECHNOLOGIES LLC; BWXT ISOTOPE TECHNOLOGY GROUP, INC.; BWXT NUCLEAR ENERGY, INC.
To: WELLS FARGO BANK, NATIONAL ASSOCIATION, AS ADMINISTRATIVE AGENT
Reel/Frame 073531/0358 →
Continuity (3)
Continuation 17515625 · Nov 1, 2021
Provisional Application 63109882 · Nov 5, 2020
Related Publication 20240001607A1 · Jan 4, 2024
References Cited (40)
US 4016226A · Kosiancic · 1977 [cited by applicant]
US 9217098B1 · Stevenson et al. · 2015 [cited by applicant]
US 10737984B2 · Schaedler et al. · 2020 [cited by applicant]
US 10993783B2 · Wu et al. · 2021 [cited by applicant]
US 11177047B2 · van Rooyen et al. · 2021 [cited by applicant]
US 20030113447A1 · Sherwood · 2003 [cited by examiner]
US 20040094058A1 · Kasperchik et al. · 2004 [cited by applicant]
US 20040265413A1 · Russell et al. · 2004 [cited by applicant]
US 20110190446A1 · Matsui et al. · 2011 [cited by applicant]
US 20130010914A1 · Garnier et al. · 2013 [cited by applicant]
US 20140113844A1 · Haque et al. · 2014 [cited by applicant]
US 20140197557A1 · Picart et al. · 2014 [cited by applicant]
US 20170021455A1 · Dallarosa et al. · 2017 [cited by applicant]
US 20170196666A1 · Bohm et al. · 2017 [cited by applicant]
US 20170287575A1 · Venneri · 2017 [cited by applicant]
US 20170326789A1 · Kimblad et al. · 2017 [cited by applicant]
US 20180148379A1 · Schaedler et al. · 2018 [cited by applicant]
US 20180326480A1 · Opschoor et al. · 2018 [cited by applicant]
US 20200070242A1 · Opschoor et al. · 2020 [cited by applicant]
US 20200308064A1 · Fisher et al. · 2020 [cited by applicant]
US 20200353681A1 · Fisher et al. · 2020 [cited by applicant]
US 20200373024A1 · Gramlich · 2020 [cited by applicant]
US 20210158978A1 · Terrani et al. · 2021 [cited by applicant]
US 20210202115A1 · Na et al. · 2021 [cited by applicant]
US 20210202116A1 · Griffith et al. · 2021 [cited by applicant]
US 20210230072A1 · Dickerson et al. · 2021 [cited by applicant]
US 20210304909A1 · Gramlich et al. · 2021 [cited by applicant]
US 20210358645A1 · Kim et al. · 2021 [cited by applicant]
International Search Report and Written Opinion dated Feb. 15, 2022, issued in corresponding International Application No. PCT/US2021/057644. [cited by applicant]
Wang et al., Point Defects in Ce—doped Y3Al5O12 crystal scintillators, Phys. Rev. B 73, 233204, Jun. 16, 2006. (Abstract only). [cited by applicant]
Hargreaves, Porosity of nuclear fuels. Nature 329, 589 (1987). https://doi.org/10.1038/329589c0. [cited by applicant]
Thomas, et al., Permeability of observed three dimensional fracture networks in spent fuel pins, Journal of Nuclear Materials 510 (2018) 613-622. [cited by applicant]
Ondracek et al., The Porosity Dependence of the Thermal Conductivity for Nuclear Fuels, Journal of Nuclear Materials 46 (1973) 253-258. [cited by applicant]
Blanchard et al., Uranium Oxide Aerosol Transport in Porous Graphite, Report PNNL-21014 (Jan. 2012) (90 pages). [cited by applicant]
Yao et al., Grain growth and pore coarsening in dense nano-crystalline UO2+x fuel pellets. United States (2017). https://doi.org/10.1111/jace.14780. [cited by applicant]
Ivanov, The model of the fission gas release out of porous fuel, Annals of Nuclear Energy, vol. 25, Issue 15, Sep. 1998, pp. 1275-1280. [cited by applicant]
Aravindan et al., Yield behavior of porous nuclear fuel (UO2), Mechanics of Advanced Materials and Structures, 23:10, (2016) 1149-1162, DOI: 10.1080/15376494.2015.1059529. [cited by applicant]
Torrent et al., Diffuse Reflectance Spectroscopy, in Methods of Soil Analysis Part 5—Mineralogical Methods, Eds. A. Ulery et al., No. 5 in the Soil Science Society of America Book Series, Madison, Wisconsin: Soil Scienc… [cited by applicant]
International Preliminary Report on Patentability dated May 19, 2023, issued in corresponding International Patent Application No. PCT/US2021/057644. [cited by applicant]
Extended European Search Report dated Apr. 22, 2024, issued in corresponding European Patent Application No. 21889892.2. [cited by applicant]