Kory Linton
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View article: ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization
ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization Open
High-density uranium nitride (UN) is a fuel candidate for several advanced nuclear reactor designs currently under development. Because there are limited UN performance data relative to fuel fabrication impurity and density variation, an i…
View article: Community Data Contribution to M.E.T.A. with ATF-relevant Hydrided Zr cladding (Coated and Uncoated)
Community Data Contribution to M.E.T.A. with ATF-relevant Hydrided Zr cladding (Coated and Uncoated) Open
Since the aftermath of the Fukushima Daiichi loss-of-coolant accident, accident-tolerant fuel (ATF) claddings have been developed to improve the coping times in such events. However, the mechanical performance of ATF cladding is crucial in…
View article: NSUF BOILER Pre-Irradiation Characterization and High Flux Isotope Reactor Experiment Design
NSUF BOILER Pre-Irradiation Characterization and High Flux Isotope Reactor Experiment Design Open
Alumina-forming austenitic (AFA) stainless steels have emerged as a candidate alloy because of their high-temperature strength, formability, cost, and compatibility with primary coolants for lead-cooled fast reactors (LFRs). This class of …
View article: Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes
Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes Open
The solubility of hydrogen in Zircaloy-4 (Zry-4) at the cladding operating temperature is near 100 wt. ppm. Above this solubility limit, excess hydrogen precipitates as δ-hydride platelets in the cladding material. Because of the effect of…
View article: Post-Irradiation Examination on Absorber Material Specimens Irradiated in the High Flux Isotope Reactor
Post-Irradiation Examination on Absorber Material Specimens Irradiated in the High Flux Isotope Reactor Open
Advanced accident-tolerant absorber material candidates are being investigated as an alternative to current absorber materials used in commercial nuclear reactors. Framatome and Oak Ridge National Laboratory developed a neutron irradiation…
View article: Neutron Irradiation Experiments
Neutron Irradiation Experiments Open
This presentation discusses the ongoing and upcoming neutron irradiation experiments within the Advanced Materials and Manufacturing Technologies (AMMT) program for the 2024 AMMT program review meeting. Ongoing and upcoming neutron irradia…
View article: Report on RIA Relevant Modified Burst Testing of ATF Cladding Materials
Report on RIA Relevant Modified Burst Testing of ATF Cladding Materials Open
The mechanical performance of accident-tolerant fuel (ATF) cladding candidates in light-water reactors (LWRs) must be similar to or better than that of current conventional nuclear fuel claddings to reduce dose to the public and ensure a t…
View article: Radiation testing of AM materials [Slides]
Radiation testing of AM materials [Slides] Open
This presentation discusses the combined irradiation testing methods, strategies, and high-level results of the Advanced Materials and Manufacturing Technologies program. Included are neutron irradiation, ion irradiation, and post-irradiat…
View article: Residual Stress Measurements of Cr-coated Cladding
Residual Stress Measurements of Cr-coated Cladding Open
Accident-tolerant fuel concepts for light-water reactor applications have been developed and tested in diverse research programs around the world. Industry teams have developed coated cladding concepts using different coating application m…
View article: Transient Mechanical Test Development for Accident Tolerant Cladding Candidates to Simulate PCMI-like Conditions
Transient Mechanical Test Development for Accident Tolerant Cladding Candidates to Simulate PCMI-like Conditions Open
This study investigates the transient mechanical response of accident tolerant fuel (ATF) cladding candidates to provide information on potential PCMI-induced deformation and failure of candidate cladding materials. The mechanical testing …
View article: The U.S. Accident Tolerant Fuels Program — Update on a National Initiative
The U.S. Accident Tolerant Fuels Program — Update on a National Initiative Open
In 2012 the U.S. Congress directed the Department of Energy’s (DOE) Office of Nuclear Energy to give priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or …
View article: POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD
POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD Open
A LOCA integral test with high burnup PWR M5 fuel rod was conducted in the Irradiated Fuel Examination Laboratory through the complete LOCA sequence: heating the LOCA sample to 300ºC and pressurizing the internal pressure to 8.27 MPa, heat…