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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
2021 Student Conference
April 8–10, 2021
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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Florent Heidet, Ehud Greenspan
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 251-273
Technical Paper | Fission Reactors/Fuel Cycle and Management | dx.doi.org/10.13182/NT13-A15782
Articles are hosted by Taylor and Francis Online.
A preliminary feasibility study is performed for a sodium-cooled breed-and-burn (B&B) fast reactor core for achieving high uranium utilization without solid fission product separation that could fit within a reactor vessel of the dimensions of SuperPRISM (S-PRISM). This 1000-MW(thermal) B&B core is to be fueled with depleted uranium with the exception of the fissile loading required for achieving initial criticality. When the fuel reaches its radiation damage limit, it is reconditioned using the melt-refining process and reloaded into the core until it runs out of reactivity.It is found that the maximum burnup at which the S-PRISM-sized B&B core can be designed to discharge its fuel is 43% fissions per initial metal atom. The corresponding uranium utilization is nearly 90 times higher than that of a light water reactor. The achievable burnup strongly depends on the fuel volume fraction but is almost insensitive to the core power density, fuel-reconditioning frequency, and duration of the fuel-reconditioning process.