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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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Latest News
Bipartisan bill aims to promote nuclear fusion development
Curtis
Cantwell
Sens. Maria Cantwell (D., Wash.) and John Curtis (R., Utah) have introduced a bill that would enable nuclear fusion energy technologies to have access to the federal advanced manufacturing production tax credit.
The companion version of the bill was introduced in the House by Reps. Carol Miller (R., W.Va.), Suzan DelBene (D., Wash.), Claudia Tenney (R., N.Y.), and Don Beyer (D., Va.)
The Fusion Advanced Manufacturing Parity Act extends the federal advanced manufacturing production credit (45X) by adding a 25 percent tax credit for companies that are domestically manufacturing fusion energy components.
Quentin Newell, Charlotta Sanders
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 253-263
Technical Paper | doi.org/10.13182/NSE13-44
Articles are hosted by Taylor and Francis Online.
The Monte Carlo (MC) method is becoming popular for three-dimensional fuel depletion analyses to compute quantities of interest in used nuclear fuel including isotopic compositions. However, there are some questions concerning the effect of MC uncertainties on predicted results in MC depletion calculations. The MC method introduces stochastic uncertainty in the computed fluxes. These fluxes are used to collapse cross sections, estimate power distributions, and deplete the fuel within depletion calculations; therefore, the predicted number densities also contain random and propagated uncertainties due to the MC solution to the neutron transport equation. The linear uncertainty nuclide group approximation (LUNGA) method was developed to calculate the propagated stochastic uncertainty in the nuclear isotopics, using the time-varying flux subjected to the power normalization constraint. Verification of the LUNGA method demonstrated that the standard deviation in the number densities and infinite multiplication factor (kinf) predicted by this method agree well with the uncertainty obtained from the statistical analysis of 100 different simulations performed with coupled MC depletion calculations. Future research includes (a) expanding the LUNGA methodology to include more nuclides, (b) fully automating the methodology, and (c) investigating the use of an axial segmented fuel rod.
