ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
G. Neale Kelly, Martial Olast, Jaak Sinnaeve
Nuclear Technology | Volume 94 | Number 2 | May 1991 | Pages 161-176
Technical Paper | Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety | doi.org/10.13182/NT91-A34539
Articles are hosted by Taylor and Francis Online.
The Commission of the European Communities, within the framework of its 1980–1984 radiation protection research program, initiated a 2-yr project in 1983 entitled “Methods for Assessing the Radiological Impact of Accidents” (MARIA). This project was continued and enlarged within the 1985–1989 research program. The main objectives of the project are (a) to develop a new probabilistic accident consequence assessment code that is modular, incorporates the best features of those codes already in use, can be readily modified to take account of new data and model developments, and is broadly applicable within the European Communities; (b) to acquire a better understanding of the limitations of current models and to develop more rigorous approaches where necessary; and (c) to quantify the uncertainties associated with the model predictions. Approximately 120 person-yr of effort have been committed to the second phase of the project, which involves contractors from 12 different organizations and institutes in the European Communities. This has led to the development of the accident consequence code COSYMA (COde SYstem from MARIA), which will be made generally available in mid-1990. The numerous and diverse studies that have been undertaken in support of this development are described, together with indications of where further effort might be most profitably directed.