Richard H Howard Group Leader/Senior R&D Staff Irradiation Engineer Contact howardrh@ornl.gov | 865.341.2432 All Publications Status report on HFIR irradiation of optimized alumina forming alloys FeCrAl fuel/clad chemical interaction in light water reactor environments Development of the generation III (ATR generation I) Plutonium-238 production target design Testing and qualification of molybdenum subcapsule welds for MiniFuel experiments In-Canal Assay of High Specific Activity 60Co at the Advanced Test Reactor... Capsule and Specimen Geometries for HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... Overcoming challenges to support US resumption of high specific activity cobalt-60 Single-phase, natural circulation annular flow measurements for cartridge loop irradiation experiments Transient Testing of Natural Circulation Flow in Cartridge Experiments... Assessment of Near-Term Fuel Screening and Qualification Needs for Nuclear Thermal Propulsion Systems HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... Design of the In-pile experiment Set (INSET) apparatus to support Nuclear Thermal Propulsion fuel and component testing.... Design and out-of-pile testing of a novel irradiation experiment vehicle to support qualification of nuclear thermal propulsion components Flow Test Plan to Support the Development of Cartridge Loops in the Versatile Test Reactor Assembly and Delivery of Rabbit Capsules for Irradiation of Prototype Metal and Nanocomposite Specimens in the High Flux Isot... Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy... Data-Driven Methodology for Predicting Isotope Production at Material Testing Reactors... Design and Encapsulation of Irradiation Experiments for Previously Irradiated Materials Overview of the Plutonium-238 Supply Program's CERMET Production Target Accelerated Irradiation Testing of Miniature Nuclear Fuel and Cladding Specimens... Design and Development of CANDU Ex-Service Garter Spring Irradiation Experiments in the HFIR... Current Neutronic Calculation Techniques for Modeling the Production of Ir-192 in HFIR... Mechanical performance of neutron-irradiated dissimilar transition joints of aluminum alloy 6061-T6 and 304L stainless steel... The Evolution of HFIR Cermet PU-238 Production Targets... Developing the Science and Technology for the Material Plasma Exposure eXperiment (MPEX)... Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar Web of Science ORCID LinkedIn Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Irradiation Engineering Group User Facilities High Flux Isotope Reactor Manufacturing Demonstration Facility
