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.
Nathan Siu, George Apostolakis
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 213-226
Technical Paper | doi.org/10.13182/NSE86-A17264
Articles are hosted by Taylor and Francis Online.
The assessment of the fire risk in nuclear power plants requires the analysis of fire scenarios within specified rooms. A methodology that integrates the fire protection features of a given room into an existing fire risk analysis framework is developed. An important component of this methodology is a model for the time required to detect and suppress a fire in a given room, called the “hazard time.” This model accounts for the reliability of fire detection and suppression equipment, as well as for the characteristic rates of the detection and suppression processes. Because the available evidence for fire detection and suppression in nuclear power plants is sparse and often qualitative, a second component of this methodology is a set of methods needed to employ imprecise information in a statistical analysis. These methods can be applied to a wide variety of problems.