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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Brian J. Laundy, Owen N. Jarvis
Fusion Science and Technology | Volume 24 | Number 2 | September 1993 | Pages 150-160
Technical Paper | Experimental Device | doi.org/10.13182/FST93-A30221
Articles are hosted by Taylor and Francis Online.
A simple computer model of the Joint European Torus (JET) tokamak has been constructed, using the neutron transport code McBEND, to assist in the interpretation of point neutron source data used for empirical calibrations of fission chambers placed near the tokamak to measure the total neutron emission from deuterium and deuterium-tritium plasmas, A satisfactory simulation of the experimental data using a 252Cf neutron source is obtained. In particular, the preferential moderation and absorption of 252Cf neutrons, compared with plasma neutrons, resulting from the buildup of equipment around the tokamak in recent years is demonstrated; this differentiation between neutron sources is a consequence of the use of a concrete filler in the spaces between the toroidal field (TF) coils. An unexpected increase in detector response is explained by the substitution of Freon for water as the TF coil coolant. Finally, the McBEND calculations are found to predict correctly the relative responses of both 235U and 238U fission chambers to 2.5- and 14-MeV plasma neutrons.