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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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.
R. L. Moore, C. D. Fletcher, C. S. Miller
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 73-85
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35200
Articles are hosted by Taylor and Francis Online.
An improved capability for modeling the transient behavior of the unique Advanced Neutron Source Reactor (ANSR) accumulator design has been developed. The ANSR accumulator behavior may now be simulated using an external model that is coupled to a RELAP5/MOD3 ANSR facility system model via a parallel virtual machine (PVM) connection. Existing RELAP5 code models were found to provide marginal results for simulating behavior of the unique ANSR accumulator design, and an improved accumulator modeling capability was desired. A new model for representing the ANSR accumulators, assessment and demonstration of that model, and the general methods by which external models may be coupled with RELAP5 system models using PVM connections are described.
