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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
C. R. Adkins
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 114-130
Technical Paper | Reactor | doi.org/10.13182/NT72-A31047
Articles are hosted by Taylor and Francis Online.
The standard definition of the breeding ratio is subject to some suspicion, since in many cases of practical interest it gives an incorrect measure of the fissile fuel doubling time and erroneous trends of the fuel cycle reactivity variation. The reasons for this behavior are given in this study, along with methods for removing the difficulties. In addition to the standard definition, the method of η weighting due to Ott and the method of reactivity weighting due to Baker and Ross (British definition) are examined. It is shown that the η weighting procedure is not much better than the standard definition, whereas the British definition can be used to give very good results for the doubling time and fuel cycle reactivity variation. The standard for comparison is a detailed explicit fuel cycle analysis of both the startup cycle and equilibrium cycle of an oxide fast reactor. With the methods given it is shown that the important quantities needed from a single fuel cycle analysis can be obtained just from a statics calculation, for the known composition at the beginning of the fuel cycle of interest (e.g., first fuel cycle). This result has significant importance for conceptual design studies and for optimization studies where many reactor calculations must be performed, precluding the use of an explicit fuel cycle depletion analysis. However, it is also shown that the equilibrium fuel cycle performance cannot be adequately predicted solely from start-of-life statics analysis. An approximate procedure is formulated to predict the equilibrium reactor composition, from which the equilibrium breeding gain, doubling time, and reactivity variation may be determined. The impetus for this approach is the need for an extremely rapid computational technique in optimization studies based on the equilibrium fuel cycle performance.