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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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ANS names 2026 Congressional Fellows
Kasper
Hayes
The American Nuclear Society has officially selected two of its members to serve as its 2026 Glenn T. Seaborg Congressional Science and Engineering Fellows. Alyssa Hayes and Benjamin Kasper will help the Society fulfill its strategic goal of enhancing nuclear policy by working in the halls of Congress, either in a congressional member’s personal office or with a committee, starting next January.
“The Congressional Fellowship program has put ANS in a unique position to provide significant technical assistance to Congress on nuclear science, energy, and technology, with great results,” said Congressional Fellowship Special Committee chair Harsh Desai, himself a former Congressional Fellow. “This once-in-a-lifetime professional development opportunity will allow them to learn the art of policymaking and potentially pursue it as part of their careers beyond the fellowship.”
James A. Turso, Robert M. Edwards, Jose March-Leuba
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 132-144
Nuclear Reactor Safety | Burnup Credit | doi.org/10.13182/NT95-A35102
Articles are hosted by Taylor and Francis Online.
A “hybrid” reactor /simulation (HRS) testing arrangement has been developed and experimentally verified using The Pennsylvania State University (Penn State) TRIGA Reactor. The HRS uses actual plant components to supply key parameters to a digital simulation (and vice versa). To implement the HRS on the Penn State TRIGA reactor, an experimental or secondary control rod drive mechanism is used to introduce reactivity feedback effects that are characteristic of a boiling water reactor (BWR). The simulation portion of the HRS provides a means for introducing reactivity feedback caused by voiding via a reduced order thermal-hydraulic model. With the model bifurcation parameter set to the critical value, the nonlinearity caused by the neutronic-simulated thermal/hydraulic coupling of the hybrid system is evident upon attaining a limit cycle, thereby verifying that these effects are indeed present. The shape and frequency of oscillation (∼0.4 Hz) of the limit cycles obtained with the HRS are similar to those observed in operating commercial BWRs. A control or diagnostic system specifically designed to accommodate (or detect) this type of anomaly can be experimentally verified using the research reactor based HRS.