Projects
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NSUF 24-4964: Irradiation Damage Rate Effect on the Dislocation Cell Structure of Additively Manufactured 316L
Additive manufacturing (AM) can fabricate complex geometries rapidly and cost...
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浏览NSUF 24-4964: Irradiation Damage Rate Effect on the Dislocation Cell Structure of Additively Manufactured 316L -
NSUF 24-4965: Impact of re-irradiation on strain-induced structure in heavy irradiated austenitic steel
The objective of this work is to understand and quantify the interaction...
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浏览NSUF 24-4965: Impact of re-irradiation on strain-induced structure in heavy irradiated austenitic steel -
NSUF 24-4967: Understanding the Remarkable Strain-Hardening Capacity of Irradiated PM-HIP 316L SS.
The objective of this project is to understand the deformation mechanism,...
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浏览NSUF 24-4967: Understanding the Remarkable Strain-Hardening Capacity of Irradiated PM-HIP 316L SS. -
NSUF 24-4969: Examination of irradiation effects on printed strain gauges
Real time strain monitoring during radiation experiments is critical for many...
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浏览NSUF 24-4969: Examination of irradiation effects on printed strain gauges -
NSUF 24-4970: Testing purity of molten salts – neutron activation analysis study
Molten salt reactors (MSR) are one of the most promising advanced nuclear...
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浏览NSUF 24-4970: Testing purity of molten salts – neutron activation analysis study -
NSUF 24-4971: In situ dual beam radiation on additively manufactured oxide dispersion strengthened alloy 718
The main objective of this proposal is to use in situ dual beam radiation...
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浏览NSUF 24-4971: In situ dual beam radiation on additively manufactured oxide dispersion strengthened alloy 718 -
NSUF 24-4972: In-situ TEM Characterization of surrogate oxides microstructure under fission gas retention and reactor-relevant temperatures using ion beam implantation
The evolution of fission gas (FG) products is the basis of several...
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浏览NSUF 24-4972: In-situ TEM Characterization of surrogate oxides microstructure under fission gas retention and reactor-relevant temperatures using ion beam implantation -
NSUF 24-4973: Nanoindentation Creep Testing and Characterization of High Temperature Irradiated HT-9 Cladding
HT-9 is a ferritic/martensitic steel alloy that is a candidate material for...
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浏览NSUF 24-4973: Nanoindentation Creep Testing and Characterization of High Temperature Irradiated HT-9 Cladding -
NSUF 24-4974: Direct Confirmation of Grain Boundary Roughening Using In Situ Irradiation
Molecular dynamics (MD) simulations are being carried out on grain boundaries...
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浏览NSUF 24-4974: Direct Confirmation of Grain Boundary Roughening Using In Situ Irradiation -
NSUF 24-4977: Quantifying gamma irradiation tolerance of high-emissivity coatings on stainless steel
Radiative heat transfer between the reactor vessel outer surface and ex-...
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浏览NSUF 24-4977: Quantifying gamma irradiation tolerance of high-emissivity coatings on stainless steel -
NSUF 24-4978: Analysis of FCCI and phase decomposition on Zr-lined U-10Mo specimens using Transmission Electron Microscopy and Atom Probe Tomography
For the past decades, the U.S. department of energy (DOE) has deployed...
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浏览NSUF 24-4978: Analysis of FCCI and phase decomposition on Zr-lined U-10Mo specimens using Transmission Electron Microscopy and Atom Probe Tomography -
NSUF 24-4979: Quantification of Zr Redistribution in Irradiated U-Zr Annular Fuel using EPMA
This RTE is focused on advancing the development of next generation metallic...
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浏览NSUF 24-4979: Quantification of Zr Redistribution in Irradiated U-Zr Annular Fuel using EPMA -
NSUF 24-4985: Three-dimensional imaging and quantification of neutron radiation induced porosity in U-10Zr fuels
Metallic fuels, in addition to offering a more excellent breeding ratio in...
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浏览NSUF 24-4985: Three-dimensional imaging and quantification of neutron radiation induced porosity in U-10Zr fuels -
NSUF 24-4986: Post Irradiation Examination of High Entropy Carbides
New high entropy carbides have favorable characteristics for high temperature...
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浏览NSUF 24-4986: Post Irradiation Examination of High Entropy Carbides -
NSUF 24-4987: Temperature effects of rhodium self-powered neutron detectors in a gamma field
Self-powered neutron detectors (SPND) have often been used as a part of the...
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浏览NSUF 24-4987: Temperature effects of rhodium self-powered neutron detectors in a gamma field -
NSUF 24-4994: Hybrid proton and heavy ion irradiation for void swelling testing
This study introduces a novel method that combines proton and heavy ion...
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浏览NSUF 24-4994: Hybrid proton and heavy ion irradiation for void swelling testing -
NSUF 24-5000: Stability limits of the gas bubble superlattice in neutron irradiated U-Mo fuel: A 3D multi-modal and multi-scale study
The proposed research aims to investigate the stability and collapse...
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浏览NSUF 24-5000: Stability limits of the gas bubble superlattice in neutron irradiated U-Mo fuel: A 3D multi-modal and multi-scale study -
NSUF 24-5002: Self-Alpha Irradiation of UO2-UB2 fuel
UO2-UB2 composite is an accident tolerant fuel with superior corrosion...
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浏览NSUF 24-5002: Self-Alpha Irradiation of UO2-UB2 fuel -
NSUF 24-5012: The Role of Helium on Microstructure Evolution in A709
Significant effort has been underway to provide a code case for use of alloy...
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浏览NSUF 24-5012: The Role of Helium on Microstructure Evolution in A709 -
NSUF 24-5016: Detailed characterization of in-service IASCC in 316 and 347 stainless steel baffle-former bolts
The objective of this project is to assess the mechanisms for initiation and...
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浏览NSUF 24-5016: Detailed characterization of in-service IASCC in 316 and 347 stainless steel baffle-former bolts