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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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 46 | Number 1 | October 1971 | Pages 112-130
Technical Paper | doi.org/10.13182/NSE71-A22339
Articles are hosted by Taylor and Francis Online.
The fuel management optimization problem within a light water moderated nuclear reactor is formulated as a multistage decision process, and the amount of fresh fuel in each zone and the shuffling schemes of reloading fuel are simultaneously determined so as to minimize the consumption of fresh fuel throughout plant life. The problem in case of a five-zone core involves about 8000 variables and about 2000 constraints on the variables. However, it is shown that the optimal refueling policy can be obtained in a reasonable length of computing time by using linear programming and, prior to the overall optimization calculation, by solving the subproblem of minimizing the stagewise consumption of fresh fuel. The optimal refueling policy results in reduction of the consumption of fresh fuel by about 10% compared with the conventional policy of uniform partial batch refueling. The essential assumption in the calculation model is that the spatial power distribution in the core does not change significantly with time and the optimal allocation of energy output (integrated power output) for each zone can be attained by optimizing the control rod programming for one core life. Three-dimensional depletion calculations are repeatedly performed to verify feasibility of the model based on that assumption.