NSUF Article
NSUF awards 13 new Super Rapid Turnaround Experiments
Wednesday, August 21, 2024 -
Calls and Awards, RTE
<!--slider--><figure class="pull-right" style="width:321px;margin: 0px 0px 15px 15px;"></figure><p class="MsoNormal">The U.S. Department of Energy’s Office of Nuclear Energy
awarded the first 13 Nuclear Science User Facilities Super Rapid Turnaround
Experiment (Super RTE) projects. Each project supports the advancement of nuclear
energy. <o:p></o:p></p><p class="MsoNormal">The 2024 Super RTE awards, totaling approximately $1.8 million,
were granted to seven principal investigators from universities, one principal
investigator from industry and five scientists from national laboratories.</p><p class="MsoNormal">The Super RTE, which opened for the first time April 1, is a
user access award process that offers an avenue for researchers to perform a broader scope
of irradiation effects studies (i.e., more samples and more access time at Nuclear
Science User Facilities partner institutions) than the traditional RTE award
process. Super RTE projects must be completed within 12 months of the
award.</p><p class="MsoNormal">The 2024 Super RTEs covered a wide range of topics to
further post-irradiation knowledge of nuclear materials. Of the 13 Super RTE
projects awarded, eight are focused on fuels or structural materials for the next
generation of reactors, and five of the projects focus on materials for the current
reactor fleet.</p><p class="MsoNormal">All experiments will look at various properties of materials
that have undergone irradiation at various reactors, doses, temperatures, times
and manufacturing methods. Researchers will characterize those samples using mechanical
testing, microstructural analysis and various microscopy techniques. <o:p></o:p></p><p>
</p><p class="MsoNormal">Super RTE proposals are expected to be solicited and awarded annually. Like
traditional RTE proposals, they will be reviewed and evaluated for technical merit,
relevancy and feasibility. The number of awards depends on the availability of
funding. The <a href="https://nsuf.inl.gov/Page/rte_techreview">Super RTE
Technical Review Process</a> provides further explanation of the review
process. Proposals must support the <a href="https://www.energy.gov/ne/about-us" target="_blank">DOE Office of Nuclear
Energy mission</a>. </p><p><span style="font-size: 18px;"><br><span style="font-weight: bold; font-size: 14px; color: rgb(0, 49, 99);">FY24 Super Rapid Turnaround Experiment award recipients</span></span></p><p class="MsoNormal"><o:p><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span><span style="font-size: 12px;"></span></o:p></p><table class="tableizer-table" style="background-color: rgb(255, 255, 255);"><thead><tr class="tableizer-firstrow" style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><th style="background-color: rgb(16, 78, 139); color: rgb(255, 255, 255);"> PI name</th><th style="background-color: rgb(16, 78, 139); color: rgb(255, 255, 255);"> Institution</th><th style="background-color: rgb(16, 78, 139); color: rgb(255, 255, 255);"> Project title</th></tr></thead><tbody><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">David Frazer</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">General Atomics</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Advanced microstructure characterization of irradiation impact on corrosion performance of SiC-SiC composite materials</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Yachun Wang</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Idaho National Laboratory</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">In-situ TEM heating investigation of M23C6 stability in neutron irradiated HT9</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Robert Okojie</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">NASA Glenn Research Center</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">In-operando performance characterization of on-chip integrated SiC pressure/temperature sensors under irradiation</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Timothy Lach</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Oak Ridge National Laboratory</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Detailed characterization of in-service IASCC in 316 and 347 stainless steel baffle-former bolts</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Caleb Massey</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Oak Ridge National Laboratory</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">The role of helium on microstructure evolution in A709</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Brandon Wilson</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Oak Ridge National Laboratory</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Neutron irradiation and PIE of ZrC coated surrogate particle fuel in IN-Pile Steadystate Extreme Temperature (INSET) Testbed</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Todd Palmer </span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Pennsylvania State University</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Interactions between neutron irradiation and oxide based inclusions in additively manufactured austenitic stainless steels</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Xing Wang</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Pennsylvania State University</span><br></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Deciphering the role of nitrogen on the performance of ferritic-martensitic steels under high-dose irradiation using N-15 isotope doping</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Jake Fay</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Rensselaer Polytechnic Institute</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Characterization of U8Pu10Zr fluff sample</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Peter Hosemann</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">University of California, Berkeley</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Understanding the effect of helium and neutron irradiation in ODS alloys</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Lin Shao</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Texas A&M University</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Accelerated evaluation of friction stir welding for on-site repairs using HFIR irradiation, welding, accelerator irradiation, and characterization</span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Patrick Warren</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">University of Texas at San Antonio</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Mechanical assessment of Pd corroded surrogate and irradiated TRISO particles </span></td></tr><tr style="background-image: !important; background-position-x: !important; background-position-y: !important; background-size: !important; background-repeat: !important; background-attachment: !important; background-origin: !important; background-clip: !important;"><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Matthew Swenson</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">University of Idaho</span></td><td style="padding: 4px; margin: 3px; border: 1px solid rgb(204, 204, 204);"><span style="font-size: 12px;">Influence of laser welding on deformation mechanisms in irradiated and weld-repaired Ni-Cr alloys</span></td></tr></tbody></table>
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