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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
J. Chao, B. B. Mikic, N. E. Todreas
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 22-33
Technical Paper | Reactor | doi.org/10.13182/NT79-A32159
Articles are hosted by Taylor and Francis Online.
Two design models illustrate the methodology used to obtain the acceptable ranges for a set of design parameters for a lithium-cooled tokamak blanket. The methodology can also be used to identify the limiting constraints for a particular design. For typical tokamaks, header diameter is ∼12 cm; coolant inlet velocity is found to be <0.1 m/s to maintain a reasonable hoop stress in the header. For the constant ’ model, where tubes are distributed to match the volumetric heat generation, the limiting constraints are found to be the total number of tubes and the maximum size of the headers that can fit radially in the blanket. The maximum first wall neutron loading is 7 MW/m2. For the constant Tmax model, where cooling channels are placed so that the peak temperatures between the channels are equal, the limiting constraint is found to be the thermal stress in the channel wall. The first wall neutron loading is found to be 2.1 MW/m2.