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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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Fusion Science and Technology
U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Renato Vinicius A. Marques, Marcia Saturnino, Felipe Martins, Carlos Eduardo Velasquez Cabrera, Claubia Pereira Bezerra Lima, Maria Auxiliadora Fortini Veloso, Antonella Lombardi Costa
Fusion Science and Technology | Volume 76 | Number 2 | February 2020 | Pages 145-152
Technical Paper | dx.doi.org/10.1080/15361055.2019.1704594
Articles are hosted by Taylor and Francis Online.
Lead-bismuth eutectic is used as a coolant for the fusion-fission hybrid system (FFS) based on a tokamak that enhances the transmutation of transuranic nuclides. However, this coolant does not produce enough tritium to supply the fusion reactions of the system. Therefore, the aim of this work is to evaluate the insertion of tritium breeder layers (TBLs) on the FFS to enhance tritium production. The analyzed materials for tritium production were beryllium, boron, and lithium alloys. The results indicate the most suitable material for tritium production depends on the TBL location. The results also indicate that there is a strong dependency on the position of the TBL affecting the neutronic parameters and nuclide transmutation such as criticality and fuel depletion. The reaction rates for tritium production and fuel composition after a fuel burnup were analyzed using the Monte Carlo N-Particle 5 (MCNP5) and MONTEBURNS codes.