ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.
Mohamed S. El-Genk, Huimin Xue, Chris Murray
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 145-166
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34813
Articles are hosted by Taylor and Francis Online.
A thermionic transient analysis model is developed to simulate transient and steady-state operations of a fully integrated, single-cell thermionic fuel element (TFE). The responses of the TFE to a step input in reactivity and changes in the cesium pressure or in the size of the interelectrode gap, the coolant temperature, and the load demand are investigated. Also, the effects of these parameters on the load electric power, emitter temperature, overall conversion efficiency, and load-following characteristics of the TFE are determined. Results show that although nuclear reactors having negative temperature reactivity coefficients are always load following, TFEs are only partially load following. For TFEs having a large interelectrode gap, it is desirable to conserve cesium by lowering its vapor pressure at the beginning of life since increasing the cesium pressure insignificantly affects the load electric power. However, should fuel swelling reduce the width of the interelectrode gap (after operating the reactor for an extended period of time), both the conversion efficiency and the load electric power will decrease. In this case, the load electric power could be restored by increasing the fission power and only partially by increasing the cesium vapor pressure.