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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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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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.
Peter J. Jensen, James F. Lang, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 279-289
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33881
Articles are hosted by Taylor and Francis Online.
A method allowing individual representation of a ruptured steam generator tube without including it explicitly in the RETRAN-02 nodalization was investigated. The resulting methodology allows accurate representation of flow through a single ruptured tube without incurring prohibitive computing costs. The study considered a wide variety of fluid conditions at the rupture ranging from subcooled liquid to two-phase fluid and from choked to unchoked rupture flow. Although only one tube rupture geometry was considered, this study provides the groundwork from which methods specific to other geometries can be easily developed. Portions of this method were compared with RELAP5 calculations and good agreement was shown. This methodology was incorporated in a RETRAN-03 analysis of a steam generator tube rupture event in a Westinghouse two-loop plant. This included a case with a tube rupture accompanied by loss of off-site power as well as a case incorporating procedures for operator actions during a tube rupture event. The results indicate both the impact and the necessity of appropriate operator actions in such an event. The RETRAN-03 computer code was found to perform satisfactorily when this tube rupture modeling technique was incorporated. Faster than “realtime” computational speed was demonstrated on a Cyber 176 computer when using a fairly detailed RETRAN plant model (54 volumes, 82 junctions).