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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Atsuyuki Suzuki, Ryohei Kiyose
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 121-134
Technical Paper | doi.org/10.13182/NSE71-A19662
Articles are hosted by Taylor and Francis Online.
The problem of optimal control rod withdrawal sequence is formulated for a multizone core model of a nuclear reactor. In particular, the maximum average burnup problem for light-water reactors is investigated to find the governing principles in optimal control rod programming. The optimal solution depends only on end-of-life (EOL) states, and in the optimal state, the control poisons are all withdrawn from the entire core and the power distribution will be as uneven as possible within the constraints on the power peaking factor. We define the core composition, including the control poison, which represents the nuclear performance of each zone and it is taken as an independent control vector. The admissible control is defined such that the control vector satisfies the criticality condition and the constraints of power peaking factor. Some complexities of the other constraints to be considered are resolved by determining the reachable region of the burnup of each zone which is chosen as a state vector. The method described in this study is based on a topological mapping theory, and for illustrative purposes, the results in the case of a two-zone model are shown by using the method.