Photon propagation modified additive manufacturing compositions and methods of additive manufacturing using same
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.
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,
wherein the nuclear fuel slurry has a composition comprising (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. %;
a dispersant >0 vol. % to 5 vol. %;
a photoabsorber greater than 0 vol. %;
a photoinitiator greater than 0 vol. %; and
at least one monomer resin 25 vol. % to <45 vol. % as a balance,
wherein a total amount of plurality of first particles and plurality of second particles is maximum 60 vol. %,
wherein the first particles have a composition including a uranium-containing material,
wherein the second particles 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, and
wherein the photoabsorber, and photoinitiator operate within an incident wavelength of 300 nm to 700 nm.
2. The method according to claim 1 , wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm equal to or greater than 0.001 Au and equal to or less than 0.7 Au or equal to or greater than 0.1 Au and equal to or less than 0.5 Au.
3. The method according to claim 1 , wherein the second particles have an absorbance for wavelengths of 300 nm to 700 nm equal to or greater than 0.001 Au to equal to or less than 0.26 Au.
4. The method according to claim 1 , wherein the second particles have a composition comprising a burnable poison or a moderator.
5. The method according to claim 1 , wherein the second particles have a composition further comprising a neutron absorber in an amount of 2 vol. % to 5 vol. %, wherein the neutron absorber has a neutron absorption cross-section of at least 60,000 barns.
6. The method according to claim 5 , wherein the neutron absorber has a composition that includes at least one element selected from the group consisting of cerium, yttrium, gadolinium, xenon and samarium.
7. The method according to claim 6 , wherein the second particles have a composition further comprising a localized stabilizer in an amount of 2 vol. % to 5 vol. %.
8. The method according to claim 7 , wherein the localized absorber has a composition that includes iron.
9. The method according to claim 1 , wherein the uranium-containing material is a uranium metal, a uranium metal alloy, a uranium ceramic, or a uranium-molybdenum alloy.
10. The method according to claim 1 , wherein the uranium-containing material is 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.
11. The method according to claim 10 , wherein the uranium-containing material is a uranium oxide or a uranium dioxide.
12. The method according to claim 1 , wherein the uranium-containing material is U(C,O,N,Si,F,Cl).
13. The method according to claim 1 , further comprising sintering the green body to form the component of the nuclear reactor system.
14. The method according to claim 1 , wherein the additive manufacturing protocol is developed using a surrogate slurry.