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
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
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.
C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 253-265
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32770
Articles are hosted by Taylor and Francis Online.
A mathematical model of corrosion product transport in the boiling water reactor (BWR) primary system has been developed. The model, which can be characterized as a semi-empirical phenomenological model, is capable of reproducing the observed data obtained in many BWRs with a variety of operational histories and a wide range of radiation levels. The results of parametric studies confirm the successful experience that the radiation fields in operating plants can be controlled and reduced by close control of the water quality in the primary system. The radiation field measured at recirculation piping of a new plant can be controlled below 200 mR/h over its entire plant life.
