Richard H Howard Group Leader/Senior R&D Staff Irradiation Engineer Contact 865.341.2432 | howardrh@ornl.gov All Publications Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731... Status memorandum on ORNL support of Vendor Irradiation Capsule design and ASME irradiation code development and new ASTM test standard development activities Mini-99 Experiment Design and Target Assembly Generation III 238Pu Production Target Hydraulic Characterization... Fuels and Materials Irradiation Testing Needs, Recent Progress, and Future Opportunities 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 Design of the In-pile experiment Set (INSET) apparatus to support Nuclear Thermal Propulsion fuel and component testing. HFIR Irradiation Testing Supporting the Transformational Challenge Reactor 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... Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy... Assembly and Delivery of Rabbit Capsules for Irradiation of Prototype Metal and Nanocomposite Specimens in the High Flux Isot... 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 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
