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June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Finding fusion’s place
Fusion energy is attracting significant interest from governments and private capital markets. The deployment of fusion energy on a timeline that will affect climate change and offer another tool for energy security will require support from stakeholders, regulators, and policymakers around the world. Without broad support, fusion may fail to reach its potential as a “game-changing” technology to make a meaningful difference in addressing the twin challenges of climate change and geopolitical energy security.
The process of developing the necessary policy and regulatory support is already underway around the world. Leaders in the United States, the United Kingdom, the European Union, China, and elsewhere are engaging with the key issues and will lead the way in setting the foundation for a global fusion industry.
L. El-Guebaly, L. Mynsberge, A. Davis, C. D’Angelo, A. Rowcliffe, B. Pint, ARIES-ACT Team
Fusion Science and Technology | Volume 72 | Number 1 | July 2017 | Pages 17-40
Technical Paper | dx.doi.org/10.1080/15361055.2016.1273669
Articles are hosted by Taylor and Francis Online.
The ARIES team has examined a multitude of fusion concepts over a period of 25 years. In recent years, the team wrapped up the Advanced Research, Innovation, and Evaluation Study (ARIES) series by completing the detailed design of the ARIES–Advanced and Conservative Tokamak (ARIES-ACT2) power plant—a plant with conservative physics and technology, representing a tokamak with reduced-activation ferritic/martensitic (RAFM) structure and dual-coolant lead-lithium blanket. The integration of nuclear assessments (neutronics, shielding, and activation) is an essential element to ARIES-ACT2 success. This paper highlights the design philosophy of in-vessel components and characterizes several nuclear-related issues that have been addressed during the course of the study to improve the ARIES-ACT2 design: sufficient breeding of tritium to fuel the plasma, well-optimized in-vessel components that satisfy all design requirements and guarantee the shielding functionality of its radial/vertical builds, survivability of low-activation/radiation-resistant structural materials in 14-MeV neutron environment, activation concerns for RAFM and corrosion-resistant oxide-dispersion-strengthened alloys, and an integral approach to handle the mildly radioactive materials during operation and after decommissioning.