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...
0 Өгөгдлийн бүрдэл
NSUF 22-4437: Neutron Irradiation Effects on the Tensile Properties of Wire Arc Additive Manufactured Grade 91 Steel -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4442: Dislocation loop and bubble evolution in helium irradiated ThO2 and UO2 single crystals -г харах -
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...
0 Өгөгдлийн бүрдэл
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. -г харах -
NSUF 22-4450: Grain Boundary Evolution During Irradiation in RPV Steels
The embrittlement of reactor pressure vessels (RPV) in light water reactors...
0 Өгөгдлийн бүрдэл
NSUF 22-4450: Grain Boundary Evolution During Irradiation in RPV Steels -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4453: Effect of neutron irradiation on the microstructure of NF616 (Grade 92) as a function of dose and temperature -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4456: Examining microstructures and mechanical properties of neutron and ion irradiated T91, HT9 and 800H alloys -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4459: Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy -г харах -
NSUF 22-4461: In situ irradiation of fission nanoprecipitates
Nuclear fuel undergoes significant microstructural and chemical evolution...
0 Өгөгдлийн бүрдэл
NSUF 22-4461: In situ irradiation of fission nanoprecipitates -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4462: Radiation Tolerant Neuromorphic Computing System using 3-D NAND Flash Memory -г харах -
NSUF 22-4465: Radiation Tolerance of Advanced Multilayered Coatings under Transient Temperature Conditions
Advance multilayered coating has proven thermal-cycle resistance and...
0 Өгөгдлийн бүрдэл
NSUF 22-4465: Radiation Tolerance of Advanced Multilayered Coatings under Transient Temperature Conditions -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4476: Probing the effect of specific chemical elements on the irradiation induced defects formation and evolution in high entropy alloys -г харах -
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,...
0 Өгөгдлийн бүрдэл
NSUF 22-4493: Mechanical response and chemical effects at the fuel-cladding interface of HT-9 and metallic fuel -г харах -
NSUF 22-4494: Accelerated Irradiation and Evaluation of Ultrastrong and Elastic Glassy Carbon
The proposed project will conduct accelerated irradiation and post-...
0 Өгөгдлийн бүрдэл
NSUF 22-4494: Accelerated Irradiation and Evaluation of Ultrastrong and Elastic Glassy Carbon -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4495: Integrated Effects of Irradiation and Flibe Salt on Fuel Pebble and Structural Graphites for Molten Salt Reactors -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 22-4496: Gamma irradiation effects on the mechanical behavior of seismic protective devices -г харах -
NSUF 22-BWXT: LWR 304 SS Core Shroud Samples
0 Өгөгдлийн бүрдэл
NSUF 22-BWXT: LWR 304 SS Core Shroud Samples -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 23-1837: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation -г харах -
NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium
Nuclear recoils within a high-purity germanium detector (HPGe) will be...
0 Өгөгдлийн бүрдэл
NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium -г харах -
NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects
To characterize irradiation-induced defects, TEM is often the go-to...
0 Өгөгдлийн бүрдэл
NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects -г харах -
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...
0 Өгөгдлийн бүрдэл
NSUF 23-1847: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys -г харах