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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Yu. Igitkhanov, B. Bazylev, I. Landman
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 34-38
PFC and FW Materials Issues | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14108
Articles are hosted by Taylor and Francis Online.
The thermal performance of the first wall (FW) monoblock module, made from carbon fiber composite (CFC) or tungsten alloy with a castellated plasma phasing surface, was analyzed for runaway electron (RE) impact under reactor conditions. A water cooling system with Cu pipes embedded into the module is used. Calculations demonstrate that, in ITER, for an expected RE pulse duration [approximately]0.1sec and deposition energy of [approximately]30MJ/m2 , the heat generation in a W monoblock occurs within a thin surface layer ([approximately]10m) which, however, does not melt. In the CFC case, heat generation occurs deep in the bulk ([approximately]1000m), but CFC does not experience brittle destruction. The intense X-ray radiation caused by runaways is strongly attenuated within a 10-mm-thick layer of W and does not pose any threat for the cooling system. For the CFC case, a small but significant heat generation caused by the RE can occur in the Cu pipe.