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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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August 2024
Nuclear Technology
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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.
D. P. Griggs, T. J. Honan
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 398-409
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32786
Articles are hosted by Taylor and Francis Online.
Northeast Utilities Service Company has performed sensitivity studies useful for modeling a loss of feedwater transient using the RETRAN code. These studies modeled the Connecticut Yankee Nuclear Power Plant, a four-loop Westinghouse pressurized water reactor. One-, two-, and three-volume steam generator secondary models were used in conjunction with a common primary side nodalization in a two-loop model. The importance of flow area of the steam generator secondary side for this transient has been investigated. A comparison of one-and two-loop models was made, along with an assessment of the differences in response between the equilibrium and nonequilibrium pressurizer models.