Projects
-
NSUF 22-4437: Neutron Irradiation Effects on the Tensile Properties of Wire Arc Additive Manufactured Grade 91 Steel
The ferritic martensitic (FM) alloy Grade 91 is a candidate material for...
Keine Datensätze
NSUF 22-4437: Neutron Irradiation Effects on the Tensile Properties of Wire Arc Additive Manufactured Grade 91 Steel ansehen -
NSUF 22-4442: Dislocation loop and bubble evolution in helium irradiated ThO2 and UO2 single crystals
The development of a quantitative relationship between radiation induced...
Keine Datensätze
NSUF 22-4442: Dislocation loop and bubble evolution in helium irradiated ThO2 and UO2 single crystals ansehen -
NSUF 22-4446: Effects of the fabrication technique and composition on microstructural evolution in uranium-molybdenum alloys neutron irradiated up to 1 dpa at low temperatures.
This proposed research will evaluate the effects of fabrication techniques...
Keine Datensätze
NSUF 22-4446: Effects of the fabrication technique and composition on microstructural evolution in uranium-molybdenum alloys neutron irradiated up to 1 dpa at low temperatures. ansehen -
NSUF 22-4450: Grain Boundary Evolution During Irradiation in RPV Steels
The embrittlement of reactor pressure vessels (RPV) in light water reactors...
Keine Datensätze
NSUF 22-4450: Grain Boundary Evolution During Irradiation in RPV Steels ansehen -
NSUF 22-4453: Effect of neutron irradiation on the microstructure of NF616 (Grade 92) as a function of dose and temperature
NF616 (Grade 92) is being considered as a candidate structural material for...
Keine Datensätze
NSUF 22-4453: Effect of neutron irradiation on the microstructure of NF616 (Grade 92) as a function of dose and temperature ansehen -
NSUF 22-4456: Examining microstructures and mechanical properties of neutron and ion irradiated T91, HT9 and 800H alloys
Ion irradiation has been considered as a surrogate for reactor irradiations...
Keine Datensätze
NSUF 22-4456: Examining microstructures and mechanical properties of neutron and ion irradiated T91, HT9 and 800H alloys ansehen -
NSUF 22-4459: Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy
Designing fuel claddings and ducts in advanced fission reactors such as the...
Keine Datensätze
NSUF 22-4459: Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy ansehen -
NSUF 22-4461: In situ irradiation of fission nanoprecipitates
Nuclear fuel undergoes significant microstructural and chemical evolution...
Keine Datensätze
NSUF 22-4461: In situ irradiation of fission nanoprecipitates ansehen -
NSUF 22-4462: Radiation Tolerant Neuromorphic Computing System using 3-D NAND Flash Memory
The key objective of this proposal is to evaluate the reliability of...
Keine Datensätze
NSUF 22-4462: Radiation Tolerant Neuromorphic Computing System using 3-D NAND Flash Memory ansehen -
NSUF 22-4465: Radiation Tolerance of Advanced Multilayered Coatings under Transient Temperature Conditions
Advance multilayered coating has proven thermal-cycle resistance and...
Keine Datensätze
NSUF 22-4465: Radiation Tolerance of Advanced Multilayered Coatings under Transient Temperature Conditions ansehen -
NSUF 22-4476: Probing the effect of specific chemical elements on the irradiation induced defects formation and evolution in high entropy alloys
In situ ion irradiations will be conducted on two families of high entropy...
Keine Datensätze
NSUF 22-4476: Probing the effect of specific chemical elements on the irradiation induced defects formation and evolution in high entropy alloys ansehen -
NSUF 22-4493: Mechanical response and chemical effects at the fuel-cladding interface of HT-9 and metallic fuel
The proposed research will perform advanced post-irradiation examination,...
Keine Datensätze
NSUF 22-4493: Mechanical response and chemical effects at the fuel-cladding interface of HT-9 and metallic fuel ansehen -
NSUF 22-4494: Accelerated Irradiation and Evaluation of Ultrastrong and Elastic Glassy Carbon
The proposed project will conduct accelerated irradiation and post-...
Keine Datensätze
NSUF 22-4494: Accelerated Irradiation and Evaluation of Ultrastrong and Elastic Glassy Carbon ansehen -
NSUF 22-4495: Integrated Effects of Irradiation and Flibe Salt on Fuel Pebble and Structural Graphites for Molten Salt Reactors
This project will investigate the irradiation response of the Flibe/fuel...
Keine Datensätze
NSUF 22-4495: Integrated Effects of Irradiation and Flibe Salt on Fuel Pebble and Structural Graphites for Molten Salt Reactors ansehen -
NSUF 22-4496: Gamma irradiation effects on the mechanical behavior of seismic protective devices
The goal of this project is to investigate the effect of gamma radiation on...
Keine Datensätze
NSUF 22-4496: Gamma irradiation effects on the mechanical behavior of seismic protective devices ansehen -
NSUF 22-BWXT: LWR 304 SS Core Shroud Samples
Keine Datensätze
NSUF 22-BWXT: LWR 304 SS Core Shroud Samples ansehen -
NSUF 23-1837: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation
This project is proposed by a collaborative team established by Boise State...
Keine Datensätze
NSUF 23-1837: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation ansehen -
NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium
Nuclear recoils within a high-purity germanium detector (HPGe) will be...
Keine Datensätze
NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium ansehen -
NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects
To characterize irradiation-induced defects, TEM is often the go-to...
Keine Datensätze
NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects ansehen -
NSUF 23-1847: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys
Many advanced reactor concepts demand pushing in-core materials to higher...
Keine Datensätze
NSUF 23-1847: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys ansehen