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.
Vijay R. Nargundkar, Tejen Kumar Basu, Om Prakash Joneja
Fusion Science and Technology | Volume 12 | Number 3 | November 1987 | Pages 380-394
Technical Paper | Blanket Engineering | doi.org/10.13182/FST87-A25070
Articles are hosted by Taylor and Francis Online.
Neutron multiplication measurements for 14-MeV neutrons were carried out in thick beryllium and graphite assemblies at the Institute for Reactor Development, Jülich, Federal Republic of Germany. Earlier Monte Carlo calculations using the ENDF/B-III library contained systematic errors that did not account for the predominant axial thermalization and non-1/v absorption in polyethylene. In addition, the calculational geometry differed considerably from the experimental geometry. These deficiencies have been eliminated in the present calculations, where the Los Alamos 30-group CLAW-IV library has been used. The anisotropy of the source in space and energy has also been taken into account. The results show that the calculated value of neutron multiplication is 20% higher (originally reported 30% higher) than the measured multiplication in beryllium. The results confirm the measurements made with BeO. For graphite and lead, excellent agreement is found between calculated and measured multiplication.
