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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.”
Luca Galbiati, Luigi Mazzocchi, Paolo Vanini
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 338-345
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35213
Articles are hosted by Taylor and Francis Online.
The simplified boiling water reactor makes use of an isolation condenser (1C) submerged in a large water pool; following a postulated accident, the pool water boils off, releasing steam to the atmosphere and ensuring passive containment cooling for at least 3 days. A further improvement is the isolation condenser pool cooling system (ICPCS), proposed by ENEL /CISE. It makes use of reflux condensing heat exchangers directly connected to the pool gas space of the IC; noncondens-able gases can be vented during the earlier phase of operation by means of a water seal mechanism operating in a passive way. The expected benefits from the ICPCS are the elimination of constraints on the “grace period” duration and the possibility of avoiding an extended release of a visible and potentially radioactive steam plume. To verify the performance both at component and system level, an instrumented ICPCS prototype, operating with a thermal power scaling factor of ∼1:615, has been built and tested at CISE laboratories, both in steady and dynamic conditions. The experimental results confirm the capability of the tested ICPCS module to operate in a safe and passive way.