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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Steven P. Nesbit, Richard J. Gerling, Gregg B. Swindlehurst
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 344-352
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34147
Articles are hosted by Taylor and Francis Online.
A comprehensive program by the Duke Power Company to qualify thermal-hydraulic transient analysis methods has been completed. The cornerstone of these methods is the use of the RETRAN-02/MOD003 computer code for the prediction of reactor coolant system behavior during plant transients. A RETRAN model of the Oconee nuclear station [three 2568-MW(thermal) Babcock & Wilcox reactors] was constructed and validated by comparison with data from actual plant events. The transient data base was searched to identify those events that are challenging to the predictive ability of the code and that have sufficient information available for a meaningful comparison between the code and the data. Nine events were selected, covering the following range of transient types: loss of primary-to-secondary heat transfer, excessive primary-to-secondary heat transfer [including steam generator (SG) overfeed and SG depressurization], loss of forced primary circulation, change in core reactivity, and operational transient without reactor trip. For each benchmark, a detailed review was made of all available sources of information in order to develop a complete set of initial and boundary conditions. The plant base model was modified to match the actual initial conditions, and the event was simulated using the best representation of the key boundary conditions. Four transient benchmarks are discussed in detail. The August 14, 1984, loss of all feedwater at Unit 3 demonstrates the effect of SG dryout on the primary system. The September 10, 1982, turbine bypass valve failure involves the posttrip overcooling of the primary system due to SG depressurization. The August 8, 1982, dropped control rod group event shows the effect of a rapid change in core reactivity on the plant. The July 15, 1985, main feedwater pump trip without reactor trip is characterized by a successful runback following a large mismatch between power generation and power removal. The accurate prediction of key phenomena during these and other events provides justification for the application of RETRAN to simulate the Oconee plant response to a wide variety of non-loss-of-coolant accident transients.