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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
May 2025
Nuclear Technology
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
John F. Geldard, Adolph L. Beyerlein
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 252-258
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34820
Articles are hosted by Taylor and Francis Online.
The mathematical basis for a new computer code, CUSEP-MOD1, is described. This new code allows the calculation of the temporal response of pulsed column contactors with sieve plates in which spent nuclear fuel is reprocessed using the Purex process. The CPU times needed for these calculations are shorter than those using the CUSEP code but longer than those using the PULSER code, these latter codes having been described previously. Although PULSER remains the faster code, it utilizes approximations that would make CUSEP-MOD1 the preferable code for many applications. The improved efficiency of CUSEP-MOD1 is based on an analysis of the correlation of the aqueous and organic flows in pulsed columns. The analysis shows that both phases move with positive correlation at zero lag time because of the magnitude of the impressed pulsed flow. The new code gives concentration profiles virtually identical to those of the CUSEP code and replaces CUSEP for calculation of the temporal and steady-state concentration profiles in pulsed column contactors. A comparison is made of the steady-state concentration profiles in an exemplary extraction (A-type) contactor calculated using CUSEP, CUSEP-MOD1, and PULSER.