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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.
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Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
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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.
Joakim Karlsson, Thomas Elevant
Fusion Science and Technology | Volume 33 | Number 3 | May 1998 | Pages 341-349
Technical Paper | doi.org/10.13182/FST98-A36
Articles are hosted by Taylor and Francis Online.
An heuristic approach has been adopted to obtain empirical scaling formulas for the dependence of neutron emission on predefined machine parameters, such as applied auxiliary heating power, plasma current IP, and toroidal magnetic field BT. The results are intended to be used to predict the neutron emission before each discharge. These formulas are of interest in their own right but more practically can be used as input to control software to pre-set the optimum precollimator apertures for neutron diagnostics such as spectrometers. Formulas have been obtained for data from plasma pulses during the years 1992 and (1994 + 1995), i.e., before and after the divertor installation and major modifications of the Joint European Torus (JET) vessel.Obtained scaling formulas for moderate beam power PNB show neutron emission after installation of the divertor to be lower than before. However, for high beam power, the scaling laws predict as large and even larger neutron emissions for the (1994 + 1995) neutral beam (NB)-heated plasmas as compared to 1992 plasmas. The dependence on radio-frequency (rf) heating power Prf is significantly larger in the scaling laws deduced prior to the divertor phase than after, which implies more efficient heating in 1992. With the exception of combined NB- and rf-heated plasma pulses, the dependence on plasma current has increased moderately after the modifications of JET. For all observations with combined NB and rf heating, the dependence on Prf is quite small, and the neutron production for this category of discharges is dominated by NB heating.A set of scaling laws is found that predicts the neutron emission within a factor of 2, which is consistent with our objective.