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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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November 2025
Latest News
Fusion office bill introduced in line with DOE reorganization plan
Cornyn
Padilla
Sens. Alex Padilla (D., Calif.) and John Cornyn (R., Texas) have introduced bipartisan legislation to formally establish the Office of Fusion at the Department of Energy. This move seeks to codify one of the many changes put forward by the recent internal reorganization plan for offices at the DOE.
Companion legislation has been introduced in the House of Representatives by Reps. Don Beyer (D., Va.) and Jay Obernolte (R., Calif.), who are cochairs of the House Fusion Energy Caucus.
Details: According to Obernolte, “Congress must provide clear direction and a coordinated federal strategy to move fusion from the lab to the grid, and this legislation does exactly that.”
Keith C. Bledsoe, Jeffrey A. Favorite, Tunc Aldemir
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 106-126
Radiation Transport and Protection | doi.org/10.13182/NT176-106
Articles are hosted by Taylor and Francis Online.
Determining the components of a radioactive source/shield system using the system's radiation signature, a type of inverse transport problem, is one of great importance in homeland security, material safeguards, and waste management. Here, the Levenberg-Marquardt (or simply "Marquardt") method, a standard gradient-based optimization technique, is applied to the inverse transport problems of interface location identification, shield material identification, source composition identification, and material mass density identification (both separately and combined) in multilayered radioactive source/shield systems. One-dimensional spherical problems using leakage measurements of neutron-induced gamma-ray lines and two-dimensional cylindrical problems using flux measurements of uncollided passive gamma-ray lines are considered. Gradients are calculated using an adjoint-based differentiation technique that is more efficient than difference formulas. The Marquardt method is iterative and directly estimates unknown interface locations, source isotope weight fractions, and material mass densities, while the unknown shield material is identified by estimating its macroscopic gamma-ray cross sections. Numerical test cases illustrate the utility of the Marquardt method using both simulated data that are perfectly consistent with the optimization process and realistic data simulated by Monte Carlo.