Clemente Parga
YOU?
Author Swipe
View article: Century: Zap Energy’s 100-kW-Scale Repetitive Sheared-Flow-Stabilized <i>Z</i> -Pinch System with Liquid Metal Cooling
Century: Zap Energy’s 100-kW-Scale Repetitive Sheared-Flow-Stabilized <i>Z</i> -Pinch System with Liquid Metal Cooling Open
View article: Progress on Multielement Spectroscopic Temperature and Impurity Studies on a High Flow Velocity Z-Pinch
Progress on Multielement Spectroscopic Temperature and Impurity Studies on a High Flow Velocity Z-Pinch Open
Multiple spectroscopy diagnostics have been fielded on the FuZE-Q sheared-flow-stabilized Z-pinch to measure plasma impurities, flow velocity, temperature, and density. The spectroscopy diagnostics currently cover the wavelengths from extr…
View article: Methods and apparatus for additively manufacturing structures using in situ formed additive manufacturing materials
Methods and apparatus for additively manufacturing structures using in situ formed additive manufacturing materials Open
A method of additively manufacturing a structure comprises nuclear reactor comprises disposing a feed material on a surface of a substrate in a reaction vessel, disposing at least one material formulated and configured to react with the fe…
View article: Oxidation behavior of welded Zry-3, Zry-4, and Zr–1Nb tubes
Oxidation behavior of welded Zry-3, Zry-4, and Zr–1Nb tubes Open
The Transient Reactor Test (TREAT) facility is a research reactor designed to simulate rapid transients to test new fuel designs. TREAT's cladding is exposed to unique conditions compared to normal water reactors. These conditions include:…
View article: Oxidation behavior of Zirconium, Zircaloy-3, Zircaloy-4, Zr-1Nb, and Zr-2.5Nb in air and oxygen
Oxidation behavior of Zirconium, Zircaloy-3, Zircaloy-4, Zr-1Nb, and Zr-2.5Nb in air and oxygen Open
View article: Characterizing surrogates to develop an additive manufacturing process for U3Si2 nuclear fuel
Characterizing surrogates to develop an additive manufacturing process for U3Si2 nuclear fuel Open
View article: M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection
M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection Open
The Idaho National Laboratory (INL) Transient Reactor Test Facility (TREAT) is a nuclear test facility designed to provide safety data for fuel designs by simulating conditions during various types of nuclear excursions. The M5 alloy cladd…
View article: Fuel – clad chemical interaction evaluation of the TREAT reactor conceptual low-enriched-uranium fuel element
Fuel – clad chemical interaction evaluation of the TREAT reactor conceptual low-enriched-uranium fuel element Open
View article: Heat Treatment Development for the TREAT LEU Fuel Zr-alloy Cladding via Time-Temperature Diagrams
Heat Treatment Development for the TREAT LEU Fuel Zr-alloy Cladding via Time-Temperature Diagrams Open
size, the Handbook has been split into two parts, which are presented as separate documents. This (the first) part contains introductory material and information about the U-Pu-Zr system (U-Zr, Pu-Zr, U-Pu, and U-Pu-Zr alloys, including th…
View article: Effect of High Si Content on U3Si2 Fuel Microstructure
Effect of High Si Content on U3Si2 Fuel Microstructure Open
View article: Room temperature mechanical properties of electron beam welded zircaloy-4 sheet
Room temperature mechanical properties of electron beam welded zircaloy-4 sheet Open
View article: Selection of Nuclear Fuel for TREAT: UO<sub>2</sub> vs U<sub>3</sub>O<sub>8</sub>
Selection of Nuclear Fuel for TREAT: UO<sub>2</sub> vs U<sub>3</sub>O<sub>8</sub> Open
The Transient Reactor Test (TREAT) that resides at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL), first achieved criticality in 1959, and successfully performed many transient tests on nuclear fuel until 1994 whe…