Joseph {Joe} M Giaquinto Senior Technical Strategist Contact GIAQUINTOJM@ORNL.GOV All Publications Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, And Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods... Fission Gas Composition, Rod Internal Pressure, And Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods... Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods... Rapid measurements of 235U fission product isotope ratios using an online, high-pressure ion chromatography inductively coupled plasma mass spectrometry protocol with comparison to isotopic depletion models Development of a Fast and Efficient Analytical Technique for the Isotopic Analysis of Fission and Actinide Elements In Environmental Matrices Trace impurity analysis in uranium oxide via hybrid quantification techniques—gravimetric standard addition and isotope dilution mass spectrometry Integration of a hyphenated HPIC-ICPMS protocol for the measurement of transplutonium isotopic mass distributions for 252Cf campaigns at 91°µÍø Method Development of a Rapid Analytical Technique for Nuclear Materials in Complex Matrices Using Isotope Dilution-High Pressure Ion Chromatography-Inductively Coupled Plasma Mass Spectrometry (ID-HPIC-ICPMS) Analysis of New Measurements of Isotopic Compositions in Spent Fuel Samples from Calvert Cliffs Unit 1 Reactor using SCALE 6.2 Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2 Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding... Workshop on Preserving High Purity Uranium-233... Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation Need for High-Purity Uranium-233 Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods... ADAPTATION OF HPLC-ICPMS MEASUREMENT PROTOCOLS FOR NUCLEAR PROJECTS AT THE OAK RIDGE NATIONAL LABORATORY Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Chemical Sciences Division Nuclear Analytical Chemistry Section
