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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
E. V. Depiante
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE93-A24493
Articles are hosted by Taylor and Francis Online.
Part of the reactor design process is performance evaluation according to predefined criteria, including reactor stability behavior under different conditions. This work focuses on the stability characterization of a reactor system with feedback under low reactor power, low reactor coolant flow conditions. Such conditions might be encountered, for example, after a loss of flow without scram in some passively safe reactor designs. Algebraic and frequency stability-criteria-based methods are developed to find stability regions, stability boundary surface in system parameter space, and frequency of oscillation at oscillatory instability boundaries. Models are developed for the reactor, its detailed thermal-hydraulic reactivity feedback path associated with coolant outlet temperature, and decay heat. Developed stability analysis tools are applied to the system model. A unique aspect is the assessment of the influence of decay heat on stability. Other selected parameters are the following: temperature coefficient of reactivity, reactor coolant flow, and natural-circulation flow. The result is a stability boundary surface in four-dimensional system parameter space and its associated frequency of oscillation surface. Adopting model parameter values from two reactors results in system parameters within the stable region. Conditions for system parameters to remain in the stable region are identified.