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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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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Hasna J. Khan, George Kosaly
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 34-45
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15975
Articles are hosted by Taylor and Francis Online.
Void fraction calculations have been performed using the subchannel drift-flux code CANAL. Using void and flow distributions in rod bundle geometry, a value of C0 has been estimated for bundle-averaged void fraction calculation in one-dimensional approximations. Successful prediction of the average void fraction is observed for the annular rod bundle geometry of the FRIGG experiment. In order to perform subchannel void fraction calculation, a C0 model has been developed for one-dimensional subchannel geometry. The implicit form of the C0 model developed accounts for void and flow conditions in the adjacent subchannels existing at the common interfaces, i.e., at the gap spacing between the subchannels. It appears that the magnitude of C0 varies between subchannels (annular rings of FRIGG geometry) but remains almost constant within each subchannel. Good agreement is observed between prediction and data for subchannel void fractions in axially uniform and nonuniform heated rod bundles.
