Task force charts growing interest in civilian maritime nuclear applications

April 10, 2026, 3:53PMNuclear NewsJonathan E. Stephens and Temi J. Adeyeye
NS Savannah, a reminder of what is possible. (Photo: U.S. National Archives)

Readers of Nuclear News will have heard of historical applications of civilian maritime nuclear power, like the merchant ship NS Savannah and the USS Sturgis floating power plant. With a few exceptions there has been little action in this area for over 50 years, and there are plenty of reasons and opinions as to why, but over the last few years the dramatic increase in interest from the maritime industry and its stakeholders has been undeniable.

ANS forms advanced reactors working group

March 5, 2021, 12:00PMANS News

Nesbit

Knowing that many ANS members are heavily involved in the development and regulatory oversight of advanced reactors, ANS Vice President/President-elect Steve Nesbit envisioned a place where members involved in the field could pool their resources, exchange ideas, and support interactions with other organizations and government agencies.

Nesbit’s vision is becoming a reality with the formation of the ANS Advanced Reactor Group. For now, it is housed within the Operations and Power Division, but the ARG will be open to other divisions as well. In fact, OPD chair Piyush Sabharwall said that input from across the ANS membership is essential for the group.

2020 ANS Virtual Winter Meeting: More on advanced nuclear reactors and power systems

November 20, 2020, 4:46PMNuclear News

The third part of the“Advanced Nuclear Reactors and Power Systems” sessions during the 2020 ANS Virtual Winter Meeting featured an examination of the status of various advanced reactors. The sessions were sponsored by the Operations and Power Division and chaired by Piyush Sabharwall of Idaho National Laboratory.

Here is an article on the first "Advanced Nuclear Reactors and Power Systems” session.

Presentation topics in the third and final session included using Modelica for system-level modeling and simulation of advanced reactors; the testing of fast-spectrum reactors’ gears and bearings in liquid sodium; and the creation of a simple core analysis tool called the Thermal hydrAulic COre Calculations using the single heAted channel meThod (TACOCAT) code.

Here are some of the highlights: