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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Samuel H. Levine
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 303-325
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32641
Articles are hosted by Taylor and Francis Online.
This educational module utilizes techniques used to calculate the core reactivity, power distribution, and isotopic inventory for the first and subsequent cores of a nuclear power plant to maintain adequate safety margins and operating lifetime for each core. Some reloading schemes studied minimize energy costs. The module is written more for classroom presentation and self-study by students than for the practicing nuclear engineer; however, the first two sections cover in-core fuel management in a way that should be helpful to a utility manager having the purview of core analysis. The major emphasis is on light water reactors, but in-core fuel management for the high temperature gas-cooled reactor and the liquid-metal fast breeder reactor is included. The module involves detailed information on the systematic application of nucleonic codes, e.g., cross-section generating codes and nodal and diffusion theory multigroup codes, to calculate the depletion and reloading of nuclear power reactors. It is not intended to be a reactor physics text, but detailed derivations of formulas, e.g., the B1 approximation in LEOPARD, FLARE recursion formula, used in the relevant nucleonic codes, are given in greater detail than normally found in a text to eliminate the “black box” use of computer codes.