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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
ANS’s Mentor Match applications open
Applications are now open for the American Nuclear Society’s newly redesigned mentoring program. Mentor Match is a unique opportunity available only to ANS members that offers year-round mentorship and networking opportunities to Society members at any point in their education.
The deadline to apply for membership in the inaugural summer cohort, which will take place July 1–August 31, is June 20. The application form can be found here.
Chunsen Shi, Jun Li, Jianxiang Zheng, Jian Zhang, Liuxuan Cao, Huifang Miao
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 919-932
Research Article | doi.org/10.1080/00295450.2023.2264515
Articles are hosted by Taylor and Francis Online.
In the event of a postulated severe accident, fission products may leak into the reactor building through the containment wall, exerting a radiological impact on the emergency response team as they are tasked with performing mitigative missions. It is thus important to estimate the potential radiological consequences of the mission before taking action so that an optimized plan can be devised to avoid putting the team in harm’s way unintentionally. Some of the most well-known accident simulation codes were attempted to do the estimation, but were found to be too time consuming to get the results, making them not suitable for emergency use. The problem evidently arises from the fact that there are too many (about 200) compartments in a typical reactor building.
In this study, the software REMADA is developed to simulate fission product dispersion in a reactor building (with about 200 compartments) within a reasonable timeframe, and to estimate the radiation doses to those who are carrying out mitigative missions in the reactor building. The results show that the software is not only fast, but also informative, to provide support for well-informed emergency decision making.