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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Juan C. Ramos, Lance J. Agee, Antonio F. Dias
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 170-178
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2860
Articles are hosted by Taylor and Francis Online.
Reported fuel failures at low peak enthalpies for highly exposed fuel during fast reactivity transients promoted the evaluation of reactivity insertion accidents (RIAs) in light water reactors with an approach different from the ultraconservative point-kinetics licensing evaluations performed in the past. On the basis of realistic estimates for the rod worth and plant conditions, an evaluation of the consequences of the RIAs has been performed. For the pressurized water reactor and boiling water reactor (BWR) cases, rod worth became the most important parameter affecting the severity of the accident. In BWRs high subcooling can adversely affect the consequences of the event. The RIA analyses have been performed using an estimation of the distribution for these parameters in an actual plant during startup. The results show that when assumptions consistent with operating procedures are used, the probability of a significant enthalpy increase due to an RIA is greatly reduced.