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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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MIT’s nuclear professional courses benefit United States—and now Australia too
Some 30 nuclear engineering departments at universities across the United States graduate more than 900 students every year. These young men and women are the present and future of the domestic nuclear industry as it seeks to develop and deploy advanced nuclear energy technologies, grow its footprint on the power grid, and penetrate new markets while continuing to run the existing fleet of reactors reliably and economically.
Drew E. Kornreich
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 282-302
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-A15784
Articles are hosted by Taylor and Francis Online.
This work involved estimating the homogeneous metal-water mixture critical mass curves of 34 fissionable nuclides from thorium to einsteinium. Calculations were performed using the discrete ordinates code PARTISN with ENDF/B-VII.0 69-group cross sections. Sample MCNP5 test cases indicate reasonable agreement between the two transport codes. In general, the results confirmed that there are three "forms" of the critical mass curves: (a) the traditional curve most well known as characterizing the "big 3" nuclides (233U, 235U, 239Pu), where the minimum critical mass is found in a dilute solution; (b) a simple monotonic curve characterized by a monotonically increasing critical mass as water is added to the metal, where the minimum critical mass is a metal system; and (c) a hybrid curve where the shape is similar to the traditional curve but the minimum critical mass is the pure metal. In general, the traditional and monotonic curves follow the "odd-even" rule of thumb that a nuclide with an even Z and an odd A or vice versa will have a traditionally shaped curve and that the other nuclides will have a monotonically shaped curve. The violations of this rule of thumb, i.e., the hybrid curves, in the set of nuclides analyzed are comprised of 232U and 252Cf. Plutonium-236 is especially interesting because it is a traditionally shaped curve with the minimum critical mass in a relatively dilute solution, but it violates the "odd-even" rule of thumb.