Projects
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NSUF 17-CINR-12849: Simulation of Radiation and Thermal Effects in Advanced Cladding Materials
The motivation of the proposed work is to understand the dynamic radiation...
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뷰 NSUF 17-CINR-12849: Simulation of Radiation and Thermal Effects in Advanced Cladding Materials -
NSUF 17-CINR-12853: HPC Access to Advance Understanding of Fission Gas Behavior in Nuclear Fuel
The outcome of this project will be improved insight into the atomistic...
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뷰 NSUF 17-CINR-12853: HPC Access to Advance Understanding of Fission Gas Behavior in Nuclear Fuel -
NSUF 17-CINR-12957: X-ray Characterization of Atomistic Defects Causing Irradiation Creep of SiC
Silicon carbide (SiC)-based accident tolerant fuel (ATF) cladding of light...
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뷰 NSUF 17-CINR-12957: X-ray Characterization of Atomistic Defects Causing Irradiation Creep of SiC -
NSUF 17-CINR-12976: Study of the Irradiation Behavior of Fast Reactor Mixed Oxide Annular Fuel with Modern Microstructural Characterization to Support Science Based Model Validation
The objective of this work is to grow the available database of post...
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뷰 NSUF 17-CINR-12976: Study of the Irradiation Behavior of Fast Reactor Mixed Oxide Annular Fuel with Modern Microstructural Characterization to Support Science Based Model Validation -
NSUF 17-CINR-12985: Irradiation, Transient Testing and Post Irradiation Examination of Ultra High Burnup Fuel
This project is intended to generate sufficient test data to inform industry...
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뷰 NSUF 17-CINR-12985: Irradiation, Transient Testing and Post Irradiation Examination of Ultra High Burnup Fuel -
NSUF 17-CINR-13004: Capacitive Discharge Resistance Welding of 14YWT for Cladding Applications
The objectives of the proposed work are to join cladding tubes of nano-...
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뷰 NSUF 17-CINR-13004: Capacitive Discharge Resistance Welding of 14YWT for Cladding Applications -
NSUF 17-CINR-13007: Irradiation of Advanced Neutron Absorbing Material to Support Accident Tolerant Fuel
A strong focus of the nuclear industry is to develop enhanced accident...
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뷰 NSUF 17-CINR-13007: Irradiation of Advanced Neutron Absorbing Material to Support Accident Tolerant Fuel -
NSUF 17-CINR-13050: Correlation between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels
The overarching goal of this project is to identify the correlations between...
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뷰 NSUF 17-CINR-13050: Correlation between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels -
NSUF 17-CINR-13073: Radiation Effects on Optical Fiber Sensor Fused Smart Alloy Parts with Graded Alloy Composition Manufactured by Additive Manufacturing Processes
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뷰 NSUF 17-CINR-13073: Radiation Effects on Optical Fiber Sensor Fused Smart Alloy Parts with Graded Alloy Composition Manufactured by Additive Manufacturing Processes -
NSUF 17-CINR-13088: Improved Understanding of Zircaloy-2 Hydrogen Pickup Mechanism in BWRs
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뷰 NSUF 17-CINR-13088: Improved Understanding of Zircaloy-2 Hydrogen Pickup Mechanism in BWRs -
NSUF 17-CINR-13106: Radiation Effects on Zirconium Alloys Produced by Powder Bed Fusion Additive Manufacturing Processes
The goal of this project is to understand the effects of radiation on...
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뷰 NSUF 17-CINR-13106: Radiation Effects on Zirconium Alloys Produced by Powder Bed Fusion Additive Manufacturing Processes -
NSUF 17-CINR-13211: Positron Annihilation Studies of Neutron Irradiated Ferritic Alloys
This request for facilities use is based on the objectives of an existing...
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뷰 NSUF 17-CINR-13211: Positron Annihilation Studies of Neutron Irradiated Ferritic Alloys -
NSUF 18-1130: Post-irradiation analysis at the nanoscale of 14YWT after high dose (16.6 dpa) neutron irradiation at 386C and 412C
The objective of this investigation is to perform detailed microstructural...
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뷰 NSUF 18-1130: Post-irradiation analysis at the nanoscale of 14YWT after high dose (16.6 dpa) neutron irradiation at 386C and 412C -
NSUF 18-1134: Understanding the Mechanism of Thermal-Hydraulic Enhancement On Gamma Irradiated Nuclear Materials Interfaces
The impact of Radiation Induced Surface Activation (RISA) on Critical Heat...
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뷰 NSUF 18-1134: Understanding the Mechanism of Thermal-Hydraulic Enhancement On Gamma Irradiated Nuclear Materials Interfaces -
NSUF 18-1144: In situ investigation of the thermomechanical performance of HCP metals and Zircaloy-4 under ion beam irradiation
In recent years, significant advances have been made in the use of ion beams...
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뷰 NSUF 18-1144: In situ investigation of the thermomechanical performance of HCP metals and Zircaloy-4 under ion beam irradiation -
NSUF 18-1146: Micro-mechanical characterization of long range order in Ni-Cr alloys and their response to radiation damage
Separate effects testing will be performed on unaged, thermally aged and...
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뷰 NSUF 18-1146: Micro-mechanical characterization of long range order in Ni-Cr alloys and their response to radiation damage -
NSUF 18-1151: Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel
The overall goal of this project is to demonstrate the use of electron...
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뷰 NSUF 18-1151: Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel -
NSUF 18-1156: Mechanical characterization of three heats (ORNL, LANL and EBR II) of HT-9 after side-by-side neutron irradiation at LWR and fast reactor relevant temperatures
HT-9 is being considered as a candidate structural material for fast,...
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뷰 NSUF 18-1156: Mechanical characterization of three heats (ORNL, LANL and EBR II) of HT-9 after side-by-side neutron irradiation at LWR and fast reactor relevant temperatures -
NSUF 18-1157: Understanding the mechanism for mesopore development in irradiated graphite by high resolution gas adsorption measurements (N2 and Kr at 77 K)
High resolution gas adsorption (N2 and Kr) at 77 K will be used to...
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뷰 NSUF 18-1157: Understanding the mechanism for mesopore development in irradiated graphite by high resolution gas adsorption measurements (N2 and Kr at 77 K) -
NSUF 18-1162: Pair distribution function analysis on recovery of irradiation induced defects in SiC
Recently, through an Advanced Fuel Campaign and NSUF RTE sponsored research...
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뷰 NSUF 18-1162: Pair distribution function analysis on recovery of irradiation induced defects in SiC