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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
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Nuclear Technology
Fusion Science and Technology
Latest News
DOE-EM finishes cleanup of legacy Oak Ridge reactor lab site
The Department of Energy’s Office of Environmental Management announced that the 30-foot-long, 37,600-pound reactor vessel from Oak Ridge National Laboratory’s Low Intensity Test Reactor was shipped to EnergySolutions’ low-level radioactive waste facility in Clive, Utah, in late April.
M.A. Hoffman, Y.T. Lee
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1557-1568
Inertial Fusion Reactor Studies | doi.org/10.13182/FST92-A29942
Articles are hosted by Taylor and Francis Online.
The HYLIFE-II concept uses the molten salt, Flibe as the primary coolant for the liquid jet flows in the reactor and uses sodium fluoroborate (NaBF4) in the secondary loop. The impact of these molten salts on the direct capital cost of the balance of plant (BOP) and on the cost of electricity (COE) has been investigated. The RUBY computer code has been written specifically for these molten salts and includes detailed analytical models for the intermediate heat exchangers (IHX's) and the steam generator system consisting of separate evaporators and superheaters. Using the RUBY code, the design of these large and costly heat exchangers and the associated tritium removal system has been optimized to yield the minimum COE. The cost models used in the code are described and the results of the optimization are given.