Projects
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NSUF 23-4681: The Role of Nb and Impurities on Nano-oxide Retention Neutron Irradiation
A range of Fe-based alloys using various compositions and processing...
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NSUF 23-4681: The Role of Nb and Impurities on Nano-oxide Retention Neutron Irradiation ansehen -
NSUF 23-4683: Neutron Detection Via Defects Created in Hexagonal Boron Nitride
Very sensitive neutron detection is possible from the changes in the optical...
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NSUF 23-4683: Neutron Detection Via Defects Created in Hexagonal Boron Nitride ansehen -
NSUF 23-4685: The effects of high-temperature creep on irradiation damages of 316H stainless steel made by laser additive manufacturing
Being simultaneously exposed to the temperature and stress in service for a...
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NSUF 23-4685: The effects of high-temperature creep on irradiation damages of 316H stainless steel made by laser additive manufacturing ansehen -
NSUF 23-4694: Mechanisms of Outstanding Radiation Tolerance in High Entropy Alloys with Nanoprecipitates
The growth of advanced energy technologies for power generation is enabled by...
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NSUF 23-4694: Mechanisms of Outstanding Radiation Tolerance in High Entropy Alloys with Nanoprecipitates ansehen -
NSUF 23-4695: Measuring the microstructural changes and elastic properties of oxidized neutron-irradiated graphite
Oxidation in nuclear graphite components can limit the lifetime of a graphite...
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NSUF 23-4695: Measuring the microstructural changes and elastic properties of oxidized neutron-irradiated graphite ansehen -
NSUF 23-4697: Gas bubble superlattice formation in metals at cryogenic temperature and in ceramics at high temperature New Proposal
In the open literature, the previous research identified both high and low...
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NSUF 23-4697: Gas bubble superlattice formation in metals at cryogenic temperature and in ceramics at high temperature New Proposal ansehen -
NSUF 23-4703: Understanding the Origin of Irradiation-Induced Yield Drop Phenomena in Grade 91
The objective of this project is to understand the origin of irradiation-...
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NSUF 23-4703: Understanding the Origin of Irradiation-Induced Yield Drop Phenomena in Grade 91 ansehen -
NSUF 23-4705: Room Temperature Tensile Properties of ATR Neutron Irradiated T91
The objective of this program is to investigate the tensile properties of T91...
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NSUF 23-4705: Room Temperature Tensile Properties of ATR Neutron Irradiated T91 ansehen -
NSUF 23-4720: Recovery of Irradiated Tantalum, a Pre-Cursor to Understanding Ferritic (BCC) Steels
We plan to establish a microstructural analogy of “separate effects testing”...
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NSUF 23-4720: Recovery of Irradiated Tantalum, a Pre-Cursor to Understanding Ferritic (BCC) Steels ansehen -
NSUF 23-4721: In situ irradiation of uranium carbide
Uranium monocarbide (UC) is a fuel material that offers several advantages...
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NSUF 23-4721: In situ irradiation of uranium carbide ansehen -
NSUF 23-4722: Investigation of evolution of defects in β-Ga2O3 under irradiation and high temperature
At the ANL’s IVEM facility, three sets of experimental conditions will be...
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NSUF 23-4722: Investigation of evolution of defects in β-Ga2O3 under irradiation and high temperature ansehen -
NSUF 23-4723: Effect of ion irradiation and dose rates on 316LY oxide-dispersion-strengthened steel additively manufactured by laser-directed energy deposition
Oxide dispersion strengthened (ODS) alloys are promising candidates for...
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NSUF 23-4723: Effect of ion irradiation and dose rates on 316LY oxide-dispersion-strengthened steel additively manufactured by laser-directed energy deposition ansehen -
NSUF 23-4724: Visualizing the root cause of dislocation channel broadening through in-situ TEM experiments
While radiation hardening is considered as one major mechanistic factor for...
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NSUF 23-4724: Visualizing the root cause of dislocation channel broadening through in-situ TEM experiments ansehen -
NSUF 23-4730: Testing of ex-core monitoring configurations at the Ohio State University Research Reactor (OSURR)
We propose to perform two experimental campaigns at the OSURR, aiming to...
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NSUF 23-4730: Testing of ex-core monitoring configurations at the Ohio State University Research Reactor (OSURR) ansehen -
NSUF 23-4733: Defect Evolution in Irradiated Superior Heat Conductors
Novel superior heat conductors, like boron arsenide (BAs), cubic boron...
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NSUF 23-4733: Defect Evolution in Irradiated Superior Heat Conductors ansehen -
NSUF 23-4737: Irradiation-Corrosion of Alumina-Forming Austenitic Stainless Steels in Static Lead
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NSUF 23-4737: Irradiation-Corrosion of Alumina-Forming Austenitic Stainless Steels in Static Lead ansehen -
NSUF 23-4738: Investigation of intergranular cracking of highly irradiated austenitic stainless steels – materials of pressurized water reactors – in ambient conditions
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NSUF 23-4738: Investigation of intergranular cracking of highly irradiated austenitic stainless steels – materials of pressurized water reactors – in ambient conditions ansehen -
NSUF 23-4739: UN multi-design irradiation campaign: a critical assessment of accelerated burnup and main correlations for mechanistic fuel performance modeling
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NSUF 23-4739: UN multi-design irradiation campaign: a critical assessment of accelerated burnup and main correlations for mechanistic fuel performance modeling ansehen -
NSUF 23-4743: Swelling Resistance of Additively Manufactured Grade 91 Steel Produced with Integrated Thermal Processing
The objective of this work is to evaluate the effectiveness of integrated...
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NSUF 23-4743: Swelling Resistance of Additively Manufactured Grade 91 Steel Produced with Integrated Thermal Processing ansehen -
NSUF 23-4744: Understanding fundamental effect of grain structure on microstructure evolution in HT9 via in-situ irradiation and TEM
Ferritic/martensitic (F/M) HT9 steels are being considered as potential...
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NSUF 23-4744: Understanding fundamental effect of grain structure on microstructure evolution in HT9 via in-situ irradiation and TEM ansehen