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.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting 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!
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Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
T. G. Theofanous, B. Najafi, E. Rumble
Nuclear Science and Engineering | Volume 97 | Number 4 | December 1987 | Pages 259-281
Technical Paper | doi.org/10.13182/NSE87-A23512
Articles are hosted by Taylor and Francis Online.
A variety of probabilistic models to quantify the likelihood of steam-explosion-induced (α-mode) containment failure from core melt accidents in commercial light water reactors have been proposed in the past. In many respects, these models and associated mechanistic considerations were complementary. Based on this and taking into account recent research efforts in this area, we perceived a need to consolidate a common approach. A new probabilistic framework is proposed for this purpose. Quantification of all inputs required by this framework is carried out, with the support of three companion parts of the study, for the case of a low-pressure core melt scenario in a pressurized water reactor (neglecting multiple explosions). The results support the generally prevalent expectation that steam explosions do not pose a significant threat to containment. To fully appreciate the qualitative limitations on this result all four parts must be carefully studied.