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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
Fusion Science and Technology
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.
Mario Dalle Donne, Walter Hame
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 111-124
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33713
Articles are hosted by Taylor and Francis Online.
Many critical heat flux (CHF) correlations have been developed for water-cooled rod clusters representing typical pressurized water reactor (PWR) or boiling water reactor fuel element geometries with relatively wide rod lattices. The fuel elements of an advanced pressurized water reactor (APWR), however, have a tight fuel rod lattice in order to increase fuel utilization. It was therefore decided to produce a new CHF correlation valid for rod bundles with tight lattices. The already available WSC-2 correlation was chosen as a basis. The geometry-dependent parameters of this correlation were again determined by root-mean-square fitting from the experimental data of CHF test performed within the framework of the light water breeder reactor program at Bettis Atomic Power Laboratory. These tests include triangular arrays of rod bundles with very tight lattices. The effects of spiral spacer ribs were based on experimental data from Columbia University. The present correlation was compared with various tests performed with rod bundles with wire wrapped spacers. Application of the new CHF correlation to conditions typical for an APWR shows that the predicted CHFs are smaller than those calculated with the usual PWR CHF correlations.