ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
Fusion Science and Technology
August 2026
Latest News
NRC issues draft EA/FONSI for Duane Arnold restart
Efforts by NextEra Energy to restart the Duane Arnold nuclear power plant as early as 2029 continue to move forward with the Nuclear Regulatory Commission's preliminary environmental assessment and determination that the restart would have no significant environmental impacts.
On Thursday, the NRC posted a draft environmental assessment and a finding of no significant impact for the Palo, Iowa, facility; the Federal Register notice was published on Monday. The Department of Energy’s Office of Energy Dominance Financing is a cooperating agency on the draft EA, as the DOE is considering providing financial assistance to the restart project.
Renan Cunha, Claubia Pereira, Daniel Campolina, Maria Auxiliadora Fortini Veloso
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 361-366
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13446
Articles are hosted by Taylor and Francis Online.
GB is a linking code developed at the Departamento de Engenharia Nuclear/UFMG to couple MCNP with the depletion and burnup capability of ORIGEN2.1. In the first version of GB, code described the behavior during the burn up of only 25 isotopes. The amount of isotopes to be considered in the simulation was increased in the GB version used in this paper (named GB5). It was simulated 75 time steps at 800kw of a Heat Pipe Power System model. Results showed that GB5 is able to generate very similar results compared to MCNPX2.6.0. The small difference encountered with the neutron flux parameter between GB5 and MCNPX2.6.0 is explained by the form that recoverable energy per fission is calculated in GB5. Radiotoxicity and radioactivity results are also presented.