ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
J. A. Haag, S. H. Levine
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 6-15
Technical Paper | Reactor | doi.org/10.13182/NT73-A31313
Articles are hosted by Taylor and Francis Online.
An experimental and analytical program has been performed to study the temperature distri bution, as a function of reactor power, in the TRIGA reactor at The Pennsylvania State Uni versity. A two-dimensional digital computer pro gram written in FORTRAN language numerically solves Poisson’s heat equation using finite dif ference techniques. Experimental measurements of the fuel tem perature in the core midplane and in the water over a large portion of the core are incorporated into the computer code, which permits determin ing the temperature distribution through the core as a function of power. Several interesting re sults were obtained, one of which showed that sub cooled boiling commences in the core between 150 and 200 kW.