b'3.2 AR CORE MATERIALSAdvanced Reactor Core MaterialsPrincipal Investigator: Tarik SalehTeam Members/Collaborators: Caleb Massey, Stuart Maloy, Mychailo Toloczko, Dalong Zhang, Jens Darsell, Ben Eftink, Ramprashad Prabhakaran, Aditya Shivprasad, Laurent Capolungo, Andre Ruybalid, Hi Tin Vo, David Hoelzerwork is ongoing to retrieve U.S. and French samples irradiated in the Phenix reactor as part of the MATRIX irradiations. In addition, through a Cooperative Research and Develop-ment Agreement with Terrapower, we are working to return the high dose irradiated HT9 specimens to Pacific Northwest National Laboratory (PNNL) after irradiation in BOR-60.Project Description:The goal of the Advanced Reactor Cladding area is to integrate our experimental and modeling capabili-ties to provide a path to qualifying future advance reactor cladding. This is done by high dose testing of irradiated cladding material and identifying legacy material available to test, as well as identifying and fabricating next generation cladding Figure 1. 14YWT NFA2 production forA dvanced Reactor Claddingmaterials, along with supply data campaign testing. In (a) the generalResearch encompassed twoand identifying data gaps that help process for 14YWT fabrication ismajor thrusts in the past fiscalour predictive multiscale modeling shown, including the mechanicalefforts. These efforts will all combine alloying of precursor powders to theiryear: International high dose fastto provide data and materials that are eventual consolidation via extrusion. Inreactor irradiations and Data Gaps/(b), comparisons of new NFA2 powderLegacy Sample inventory informingavailable for the next generation of (2022) is compared with historicalmodeling efforts. Through the U.S.advanced reactors.14YWT heats, showing improvements in impurity control Department of Energy - JapaneseAccomplishments:Atomic Energy Association CivilianLevel 2 milestone was completed: Nuclear Working Group (DOE-JAEACurrent research and technology CNWG) preparations are beinggaps related to candidate fast reactor made for inserting HT9 and 14YWTcladding materials HT9 and cold in a JOYO irradiation in CY 2026.worked D9; A summary of HT9 and Through the French AlternativeCWD9 cladding properties, design Energy and Atomic Energy Commis- equations, and data gaps, led by sion (CEA)-DOE bilateral agreementAditya Shivprasad and Tarik Saleh 152 2023|AFC ACCOMPLISHMENTS'