The Department of Energy’s funded Nuclear Science User Facility (NSUF) offers a wide range of research opportunities for nuclear energy researchers and connects researchers with desired nuclear research infrastructure. Users are provided access (at no cost to the researcher) to world-class nuclear research facilities, technical expertise from experienced scientists and engineers, and assistance with experiment design, assembly, safety analysis and examination. While the core of NSUF facilities are at Idaho National Laboratory (INL) several university (including UCB) and other national laboratories facilities are part of the NSUF network. A complete description of NSUF and the partner facilities can be found here (link)
UC-Berkeley’s nuclear materials infrastructure is part of the NSUF since 2011 and fulfilled a range of user projects as listed further below. Most equipment listed on the facilities page can be used through NSUF user proposals. We highly encourage interested users to contact the facility lead Peter Hosemann (firstname.lastname@example.org) for further information and to coordinate proposals.
Past and Current NSUF projects
“Nanohardness Measurements on Neutron Irradiated Steel Samples for Next Generation Reactors” PI: Saleh, Tarik (LANL)
“A Bootstrapping Approach to Optimizing the Fidelity of Ion Versus Neutron Irradiations” PI: Odette, G.Robert (UCSB)
“Investigation of the interface strength for matrix-fiber interface of irradiated SiC composite materials” PI: Katoh, Yutai (ORNL)
“Nanoindentation investigations of neutron-irradiated Fe-Cr-C ternary model alloys” PI: Stubbins, James (UIUC)
“Localized mechanical property assessment of neutron irradiated SiC/SiC composites at elevated temperature” PI: David Frazer (UCB)
“Micromechanical testing of Sintered UO2 fuel pellets with Controlled Microstructure” PI: Lian, Jie (RPI)
“Micromechanical properties of interfacial elements in advanced SiC composite and its environmentally protective coatings” PI: Katoh, Yutai (ORNL)
“Hardness profiling of ion irradiated 15-15Ti cladding steel using CSM nano-indentation” PI: Cauterts, Niels (SCK-CEN)
“Characterization of Grain Boundary Damage in Highly Irradiated Specimens Exposed to Irradiation Assisted Stress Corrosion Cracking.” PI: Teysseyre, Sebastien (INL)
Highlights and papers published
more to come soon.
C.Howard, C.D.Judge, D.Poff, S.Parker, M.Griffiths, P.Hosemann, “A novel in-situ, lift-out, three-point bend technique to quantify the mechanical properties of an ex-service neutron irradiated inconel X-750 component”; Journal of Nuclear Materials; 498, (2018) 149-158