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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
E. L. Simmons, Donald J. Dudziak, S. A. W. Gerstl
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 317-340
Technical Paper | Reactor | doi.org/10.13182/NT77-A31797
Articles are hosted by Taylor and Francis Online.
The final design of a nuclear reactor and any component thereof evolves through an iterative process that necessitates the evaluation of many alternative concepts. In particular, conceptual and preliminary reactor systems studies require many quick survey calculations to determine changes of certain important design parameters in response to changes of layout, material compositions, and other design features. Effective methods to perform such design sensitivity analyses are described and applied to the nuclear design of a fusion reactor. Generalized perturbation theory is used to calculate sensitivities of integral nuclear design parameters to certain design changes. The accuracy of this method is evaluated for specific cases where large ranges of design perturbations are considered. Specifically, the effects on tritium breeding, energy deposition, atom displacements and transmutations in the Reference Theta-Pinch Reactor design due to variations in the beryllium thickness, choices of molybdenum, vanadium, or niobium structural material, BeO versus beryllium neutron multiplier, graphite region thickness, and 6Li enrichment are investigated.