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
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
U. S. Rohatgi
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 100-106
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33599
Articles are hosted by Taylor and Francis Online.
The TRAC series of codes was developed to simulate pressurized water reactors (PWRs) and boiling water reactors (BWRs) under hypothetical accident conditions. The thermal hydraulics of these codes are based on a two-fluid formulation. These codes were applied to the Dartmouth College countercurrent flow tests to assess the ability of the interfacial momentum transfer models in the code to predict the countercurrent behavior. The TRAC-BD1 code, developed for the BWR analysis, qualitatively predicted the proper countercurrent flow behavior, but always overpredicted the liquid downflow. This led to the conclusion that interfacial momentum transfer in the annular regime was underestimated. The PWR version of the TRAC code, TRAC-PF1, had better agreement with the data but computed unusual behavior for the 0.152-m-i.d. pipe due to the use of Dukler’s correlation outside the data base. The code prediction improved when Bharathan-Wallis’ correlation was incorporated into this code. The correlations based on cocurrent data were not accurate in predicting countercurrent flows.