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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
J. C. Helton,* R. L. Iman, J. D. Johnson,+, C. D. Leigh
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 320-342
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16075
Articles are hosted by Taylor and Francis Online.
An uncertainty and sensitivity analysis of the MAEROS model for multicomponent aerosol dynamics is presented. Analysis techniques based on Latin hypercube sampling and regression analysis are used to study the behavior of a two-component aerosol in a nuclear power plant containment for a transient accident with loss of alternating current power (i.e., a TMLB’ accident). Conditional on assumed ranges and distributions for selected independent variables (e.g., initial distributions and mass loadings for each component, temperature, pressure, shape factors), estimates are made for distributions of model predictions and for the independent variables that influence these predictions. The analysis indicated that, for the situation under consideration, variables related to agglomeration (e.g., dynamic shape factor, material density, agglomeration shape factor, and turbulence dissipation rate) tended to dominate the observed variability. For comparison, an analysis based on differential techniques is also given. Furthermore, a study of the effects on MAEROS predictions due to the number of particle size classes and the particle size class boundaries is presented. This analysis was performed as part of a project to develop a new system of computer codes (i.e., the MELCOR code system) for use in risk assessments for nuclear power plants.