Projects
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NSUF 24-4883: Phase Field Modeling of Irradiation-Induced Crystallization in Amorphous Nuclear Oxides
The objective of this project is to understand the relative degree of...
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浏览NSUF 24-4883: Phase Field Modeling of Irradiation-Induced Crystallization in Amorphous Nuclear Oxides -
NSUF 24-4884: Investigating the effect of Te embrittlement and depleted Uranium on IN617 in molten salt conditions
The objective of the work is to investigate the role of fission product Te on...
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浏览NSUF 24-4884: Investigating the effect of Te embrittlement and depleted Uranium on IN617 in molten salt conditions -
NSUF 24-4889: Study of the behavior under ion irradiation of amorphous oxide protective coatings developed for lead fast reactors
The outstanding properties of a-Al2O3 coatings are strictly related to their...
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浏览NSUF 24-4889: Study of the behavior under ion irradiation of amorphous oxide protective coatings developed for lead fast reactors -
NSUF 24-4892: In-situ irradiation of ZrC and ZrN above 800 C
ZrC and ZrN are promising materials as components in nuclear fuels, like...
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浏览NSUF 24-4892: In-situ irradiation of ZrC and ZrN above 800 C -
NSUF 24-4893: Phase stability of partially-stabilized-zirconia under irradiation
Yittria-stabilized-zirconia (YSZ) is a promising ceramic material for...
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浏览NSUF 24-4893: Phase stability of partially-stabilized-zirconia under irradiation -
NSUF 24-4900: APT study of HT-9 to evaluate the effect of neutron irradiation temperature, alloying elements and heat treatment
Ferritic-martensitic steels are being considered as candidate structural...
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浏览NSUF 24-4900: APT study of HT-9 to evaluate the effect of neutron irradiation temperature, alloying elements and heat treatment -
NSUF 24-4911: Electron spin properties of boron vacancies in hexagonal boron nitride single crystals created by neutron irradiation
The negatively charged boron vacancy (VB-) in hexagonal boron nitride (hBN)...
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浏览NSUF 24-4911: Electron spin properties of boron vacancies in hexagonal boron nitride single crystals created by neutron irradiation -
NSUF 24-4923: Thermal stability of solute-defect clusters in structural alloys under irradiated environments
In the development of structural alloys for nuclear applications, radiation...
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浏览NSUF 24-4923: Thermal stability of solute-defect clusters in structural alloys under irradiated environments -
NSUF 24-4928: Examination of ion irradiated Additive Friction Stir Manufactured metastable high entropy alloy
In order to enhance the long-term viability and competitiveness of the...
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浏览NSUF 24-4928: Examination of ion irradiated Additive Friction Stir Manufactured metastable high entropy alloy -
NSUF 24-4932: A novel high-throughput method for quantification of materials swelling via microscale dilation techniques
Material swelling is a key microstructural degradation pathway during...
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浏览NSUF 24-4932: A novel high-throughput method for quantification of materials swelling via microscale dilation techniques -
NSUF 24-4938: Synergetic Effects of Irradiation, Temperature, and Strain on Ordering in Ni-Based Alloys
The objective of this project is to understand how irradiation, thermal...
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浏览NSUF 24-4938: Synergetic Effects of Irradiation, Temperature, and Strain on Ordering in Ni-Based Alloys -
NSUF 24-4939: Porosity Evolution in High Burnup and Low Irradiation Temperature U-10wt.%Zr Fuel Subregions
This project aims to investigate the influence of low temperatures and high...
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浏览NSUF 24-4939: Porosity Evolution in High Burnup and Low Irradiation Temperature U-10wt.%Zr Fuel Subregions -
NSUF 24-4941: Measurement of Fission Product production yields
Hundreds of nuclides can be produced in the fission of actinides. An accurate...
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浏览NSUF 24-4941: Measurement of Fission Product production yields -
NSUF 24-4943: Low fluence effects of neutron irradiation on the phase evolution of U-10wt.%Zr specimens
Currently, advanced fast reactors are under consideration for deployment....
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浏览NSUF 24-4943: Low fluence effects of neutron irradiation on the phase evolution of U-10wt.%Zr specimens -
NSUF 24-4945: TEM characterization of neutron irradiated HT-9 as a function of irradiation temperature and dose
Ferritic-martensitic (F-M) steels are being considered as candidate in-core...
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浏览NSUF 24-4945: TEM characterization of neutron irradiated HT-9 as a function of irradiation temperature and dose -
NSUF 24-4950: Post-test tensile fractography and microstructure of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550°C
The objective of this program is to investigate the strain hardening and...
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浏览NSUF 24-4950: Post-test tensile fractography and microstructure of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550°C -
NSUF 24-4952: Advanced characterization of irradiated FAST aLEU U-Mo rodlets using Transmission Electron Microscopy and Atom Probe Tomography
Low-enriched uranium (U) alloyed with molybdenum (Mo), U-Mo fuels, such as...
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浏览NSUF 24-4952: Advanced characterization of irradiated FAST aLEU U-Mo rodlets using Transmission Electron Microscopy and Atom Probe Tomography -
NSUF 24-4956: Thermal Conductivity Measurements of Irradiated Annular Low Burn-Up U-10Zr Fuel
The objective of the proposed work is to measure the local thermal...
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浏览NSUF 24-4956: Thermal Conductivity Measurements of Irradiated Annular Low Burn-Up U-10Zr Fuel -
NSUF 24-4961: Concentration Measurements of Helium and Boron in Degraded Stainless Steel Nuclear Plant Components
This project will characterize trace levels of helium, boron, and lithium in...
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浏览NSUF 24-4961: Concentration Measurements of Helium and Boron in Degraded Stainless Steel Nuclear Plant Components -
NSUF 24-4962: High Temperature Testing of Fully Ceramic Microencapsulated Fuel
Fully ceramic microencapsulated (FCM) fuel forms have been developed to...
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浏览NSUF 24-4962: High Temperature Testing of Fully Ceramic Microencapsulated Fuel