Projects
-
NSUF 18-1163: Evaluation of Irradiated Cr Coatings on Zirconium Alloys
The Westinghouse Accident Tolerant Fuel (ATF) utilizes 20 to 30 micron thick...
0資料集
瀏覽 NSUF 18-1163: Evaluation of Irradiated Cr Coatings on Zirconium Alloys -
NSUF 18-1165: Elevated Temperature In-situ SEM micro compression of UO2
Micro compression pillars will be used to measure the yield stress and...
0資料集
瀏覽 NSUF 18-1165: Elevated Temperature In-situ SEM micro compression of UO2 -
NSUF 18-1168: TEM in situ 4-point bend fracture testing of irradiated ODS alloys
The objective of this work is to evaluate fracture properties of irradiated...
0資料集
瀏覽 NSUF 18-1168: TEM in situ 4-point bend fracture testing of irradiated ODS alloys -
NSUF 18-1176: Atom Probe Tomography Investigations of nm-Scale Precipitates in Reactor Pressure Vessel Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment
This proposal covers APT characterization of a set of key RPV alloys to build...
0資料集
瀏覽 NSUF 18-1176: Atom Probe Tomography Investigations of nm-Scale Precipitates in Reactor Pressure Vessel Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment -
NSUF 18-1177: Atom probe tomography of fission gas bubble superlattice in U-Mo fuel
It has been postulated that bubble superlattice is an effective mechanism to...
0資料集
瀏覽 NSUF 18-1177: Atom probe tomography of fission gas bubble superlattice in U-Mo fuel -
NSUF 18-1178: In situ study of “rim effect” microstructure modification of nuclear fuels (resubmitted)
[With the positive reviewers' comments from previous RTE call, this proposal...
0資料集
瀏覽 NSUF 18-1178: In situ study of “rim effect” microstructure modification of nuclear fuels (resubmitted) -
NSUF 18-1179: Microstructural characterization of ~7% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
0資料集
瀏覽 NSUF 18-1179: Microstructural characterization of ~7% burn-up MOX fuel -
NSUF 18-1181: In situ TEM observation of microstructural evolution of silicon carbide (SiC)-nanostructured ferritic alloy (NFA) composite under high temperature ion irradiation
Methods: This proposal is to use the Intermediate Voltage Electron Microscopy...
0資料集
瀏覽 NSUF 18-1181: In situ TEM observation of microstructural evolution of silicon carbide (SiC)-nanostructured ferritic alloy (NFA) composite under high temperature ion irradiation -
NSUF 18-1192: Synchrotron X-ray Characterization of the Microstructural Evolution of U Alloys Irradiated to Low Fluences
Metallic fuels are relevant to many reactor types, including advanced...
0資料集
瀏覽 NSUF 18-1192: Synchrotron X-ray Characterization of the Microstructural Evolution of U Alloys Irradiated to Low Fluences -
NSUF 18-1194: Transmutation doping of hexagonal boron nitride
The electrical and optical properties of hexagonal boron nitride, a wide...
0資料集
瀏覽 NSUF 18-1194: Transmutation doping of hexagonal boron nitride -
NSUF 18-1198: Extension and Validation of Rate Theory Model of Nanocluster Irradiation Evolution: An Atom Probe Tomography Study
The objective of this study is to extend a nanocluster irradiation evolution...
0資料集
瀏覽 NSUF 18-1198: Extension and Validation of Rate Theory Model of Nanocluster Irradiation Evolution: An Atom Probe Tomography Study -
NSUF 18-1203: Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys
The objective of this research program is to establish the microstructure-...
0資料集
瀏覽 NSUF 18-1203: Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys -
NSUF 18-1207: Irradiation-induced precipitation/segregation in dual-phase Al0.3CoCrFeNi alloy
The objective of this proposal is to study irradiation-induced...
0資料集
瀏覽 NSUF 18-1207: Irradiation-induced precipitation/segregation in dual-phase Al0.3CoCrFeNi alloy -
NSUF 18-1210: Irradiation-induced solute clustering behavior in ferritic/martensitic alloy T91
The objective of this project is to evaluate the mechanism of irradiation-...
0資料集
瀏覽 NSUF 18-1210: Irradiation-induced solute clustering behavior in ferritic/martensitic alloy T91 -
NSUF 18-1211: Investigation of radiation-generated phases in FeCrSi alloys for multimetallic layered composite (MMLC) for LWR fuel cladding
A team of researchers led by MIT are developing a multimetallic layered...
0資料集
瀏覽 NSUF 18-1211: Investigation of radiation-generated phases in FeCrSi alloys for multimetallic layered composite (MMLC) for LWR fuel cladding -
NSUF 18-1213: Investigation of gas bubble behavior in metals using in-situ Ne, Ar and Kr ion irradiation
The development of He and Xe bubbles in structural and fuel materials could...
0資料集
瀏覽 NSUF 18-1213: Investigation of gas bubble behavior in metals using in-situ Ne, Ar and Kr ion irradiation -
NSUF 18-1226: In Situ TEM Investigation on Fission Gas Behavior in U-10Zr
Gaseous fission products such as Xe and Kr form bubbles within nuclear fuel...
0資料集
瀏覽 NSUF 18-1226: In Situ TEM Investigation on Fission Gas Behavior in U-10Zr -
NSUF 18-1234: In situ Ion Irradiation of a SiC composite using a MEMS-based Heating Holder
SiC composites have been a recent focus for nuclear materials research due to...
0資料集
瀏覽 NSUF 18-1234: In situ Ion Irradiation of a SiC composite using a MEMS-based Heating Holder -
NSUF 18-1237: Kinetics of irradiation defect annealing and thermal conductivity recovery in silicon carbide at high temperature
The objective of this project is to enhance understanding of the annealing of...
0資料集
瀏覽 NSUF 18-1237: Kinetics of irradiation defect annealing and thermal conductivity recovery in silicon carbide at high temperature -
NSUF 18-1242: Quantification of porosity evolution in ion irradiated metal-1D/2D nanocomposites and gas-embrittled steels via Positron Annihilation Spectroscopy
The proposed project aims to quantify and compare porosity evolution in ion...
0資料集
瀏覽 NSUF 18-1242: Quantification of porosity evolution in ion irradiated metal-1D/2D nanocomposites and gas-embrittled steels via Positron Annihilation Spectroscopy