ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Ribbon-cutting scheduled for Advanced Manufacturing Collaborative
Energy Secretary Chris Wright will attend the opening of the Advanced Manufacturing Collaborative in Aiken, S.C., on August 7. Wright will deliver remarks and join Savannah River National Laboratory leadership and partners for a ribbon-cutting ceremony.
T. W. Kerlin
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 120-130
Technical Paper | doi.org/10.13182/NSE67-A18048
Articles are hosted by Taylor and Francis Online.
A systematic procedure is presented for calculating the least stable condition in a reactor system that can occur within the uncertainty range on system parameters. This uncertainty range is due to the impossibility of perfectly predicting design parameters and the effect of aging of the system on these parameters. The method uses the linear approximation to the system dynamics equations and a steepest ascent extremum-seeking procedure. The procedure can also be reversed to determine design changes needed to give greater system stability. The applicability of the method for solving practical reactor problems has been demonstrated in an analysis of the Molten Salt Reactor Experiment using a computer program developed to implement the method. In this paper, the method is illustrated with a small sample problem.