Prospects for additive manufacturing of nuclear fuel forms
AT Nelson - Progress in Nuclear Energy, 2023 - Elsevier
Additive manufacturing (AM) is viewed as a critical enabling technology for achieving
superior performance and improved economics across many sectors. Although the past …
superior performance and improved economics across many sectors. Although the past …
Zirconium nanoparticle coating development for FCCI diffusion barrier in nuclear cladding
Fuel clad chemical interaction (FCCI) is a pervasive issue for metallic nuclear fuels. FCCI
can damage cladding, reduce thermal efficiency, and compromise the structural integrity of …
can damage cladding, reduce thermal efficiency, and compromise the structural integrity of …
Solidification-induced nonuniformity in U–Zr–RE metallic nuclear fuel rods
Metallic fuel is being developed for the next generation of sodium-cooled fast reactors due to
its safety and fuel cycle economics through spent fuel reprocessing technology. After spent …
its safety and fuel cycle economics through spent fuel reprocessing technology. After spent …
The formation mechanism of the Zr rind in U-Zr fuels
The Zr-rich rind that forms at the fuel-cladding interface in U-Zr nuclear fuels has been
known for many years, although it has never been explained. It acts as an effective diffusion …
known for many years, although it has never been explained. It acts as an effective diffusion …
Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen
Abstract Uranium-molybdenum (U-Mo) alloys show promise as a nuclear fuel system due to
their high thermal conductivity and fuel loading capability. However, U-Mo systems are …
their high thermal conductivity and fuel loading capability. However, U-Mo systems are …
Point defects stability, hydrogen diffusion, electronic structure, and mechanical properties of defected equiatomic γ (U, Zr) from first-principles
At present, many experimental fast reactors have adopted alloy nuclear fuels, for example, U-
Zr alloy fuels. During the neutron irradiation process, vacancies and hydrogen (H) impurity …
Zr alloy fuels. During the neutron irradiation process, vacancies and hydrogen (H) impurity …
Effect of additive (Zr) and dopants (Pd & Sb) on the depth of migration of lighter lanthanides (Nd & Ce) from U-bearing metal alloys into T91 steel
N Janardhanan, UK Maity, G Natarajan… - Journal of Nuclear …, 2023 - Elsevier
The metal alloy fuel, which is considered as the advanced nuclear fuel, has its own
limitations; namely, lower liquidus temperature, higher swelling, and is highly prone to …
limitations; namely, lower liquidus temperature, higher swelling, and is highly prone to …
Nd, SbNd and Sb3Nd4 and their interactions with the cladding alloy HT9
Lanthanide fission products, such as neodymium, formed during the irradiation of metallic
fuels are known to cause deleterious effects from chemical interactions occurring at the fuel …
fuels are known to cause deleterious effects from chemical interactions occurring at the fuel …
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy
Abstract Antimony (Sb) and tellurium (Te) were investigated as potential additives for U-10Zr
(wt.%) metallic fuel to limit the fuel-cladding chemical interaction (FCCI) with HT-9 alloy …
(wt.%) metallic fuel to limit the fuel-cladding chemical interaction (FCCI) with HT-9 alloy …
Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels
In uranium-based fuels, production and migration of lanthanide fission products and
subsequent chemical interactions with cladding constituents lead to fuel–cladding chemical …
subsequent chemical interactions with cladding constituents lead to fuel–cladding chemical …