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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Andhika F. Wibisono (Univ of Cambridge), Jeong Ik Lee (KAIST), Eugene Shwageraus (Univ of Cambridge)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1056-1065
Nuclear power plants (NPPs) are known to be used as providers of base-load power. As the share of the intermittent renewables in the energy mix increases, the maneuvering (load-following) of NPPs is becoming more important. Previous studies have found that combining Light Water Reactors (LWRs) with external superheater would improve their cycle thermal efficiencies and maneuvering capabilities. Implementation of this concept in a small modular boiling water reactor (SMBWR) might offer additional benefits, such as vessel size reduction and further boost of cycle thermal efficiency at higher operating pressure. This paper presents a preliminary design of hybrid SMBWR, focusing on the effect of system pressure on reactor capability to operate with natural recirculation of coolant and on steam cycle thermodynamic performance. It is demonstrated that hybrid SMBWR has natural circulation system operating at higher pressure than the conventional system by increasing its chimney height. The study of the effect of system pressure on power cycle thermodynamic performance was done by considering both fossil fuel heat and renewable heat as the potential heat source for the external superheater. The cycle thermal efficiency of hybrid SMBWR with fossil heat option varies between 40 to 42% depending on the system operating pressure while the values for renewable heat option are between 38 to 40%.