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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
Technology of Fusion Energy (TOFE)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Huntington B/C
Session Chair:
Tim D. Bohm (Univ. Wisconsin, Madison)
Alternate Chair:
Paul W. Humrickhouse
Session Organizer:
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Status of Design Activities of the DEMO Helium Cooled Pebble Bed Breeding Blanket in Europe
Guangming Zhou (Karlsruhe Institute of Technology), Francisco A. Hernandez (EUROfusion Programme Management Unit & Karlsruhe Institute of Technology (KIT)), Jarir Aktaa (Karlsruhe Institute of Technology ), David Alonso (ESTEYCO), Frederik Arbeiter (Karlsruhe Institute of Technology ), Lorenzo V. Boccaccini (Karlsruhe Institute of Technology ), Ion Cristescu (Karlsruhe Institute of Technology ), Antonio Froio (Politecnico di Torino), Christophe Garnier (CEA), Mathias Jetter (Karlsruhe Institute of Technology ), Xue Z. Jin (Karlsruhe Institute of Technology ), Marc Kamlah (Karlsruhe Institute of Technology ), Béla Kiss (Budapest University of Technology and Economics (BME)), Christina Koehly (Karlsruhe Institute of Technology ), Christine Klein (Karlsruhe Institute of Technology ), Ivan A. Maione (Karlsruhe Institute of Technology ), Luis Maqueda (ESTEYCO), Carlos Moreno (CIEMAT), Ivo Moscato (University of Palermo & EUROfusion Programme Management Unit), Iole Palermo (CIEMAT), Jin H. Park (Karlsruhe Institute of Technology ), Volker Pasler (Karlsruhe Institute of Technology ), Dario Passafiume (Karlsruhe Institute of Technology ), Pavel Pereslavtsev (Karlsruhe Institute of Technology ), Anoop Retheesh (Karlsruhe Institute of Technology ), Álvaro Yáñez (ESTEYCO)
Paper
Tritium Breeding and Nuclear Heating Evaluation of Solid Breeder Concepts
Felipe S. Novais (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville), G. Ivan Maldonado (Univ. Tennessee, Knoxville)
Calibration of a Mesoscale Tritium Transport Model for Ceramic Breeder Materials in TMAP8 Using Experimental Data
Pierre-Clement A. Simon (INL), Paul W. Humrickhouse (ORNL), Alexander D. Lindsay (INL), Masashi Shimada (INL)
Reference
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