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
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
Antares achieves zero-power criticality at INL
Leveraging more than $140 million in private capital fundraising, over 322,000 square feet of operational manufacturing space, and multifaceted partnerships with the Departments of Energy and Defense, reactor start-up Antares has become the first company involved in the Reactor Pilot Program to achieve zero-power fueled criticality—a full month ahead of the July 4 deadline set by President Trump’s Executive Order 14301.
This milestone, announced yesterday, was achieved with the company’s Mark-0: a sodium heat-pipe-cooled, TRISO-fueled microreactor. The Mark-0 is a forerunner to the company’s flagship design, which it calls the R1. For Antares, this development represents a key validation of its reactor physics, control systems, and supply chain.
X. N. Hao, J. J. Sha, J. X. Dai, J. Li, J. Lv, X. L. Yang, H. K. Yoon
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 163-170
Technical Paper | doi.org/10.13182/FST13-761
Articles are hosted by Taylor and Francis Online.
Tungsten and CuCrZr alloy have been considered as the potential candidates for armor and heat sinking materials of plasma-facing components (PFCs) because of their attractive mechanical, nuclear and physical properties. However, due to the incompatibility of the coefficient of thermal expansion and the elastic properties between the W and the Cu alloy as well as the nonhomogeneous temperature distribution in PFCs, one of the crucial issues is the generation of thermal stresses in W/CuCrZr PFCs on cooling either during fabrication or during operation of a fusion reactor. In the current work, the thermo-mechanical analysis of W/Cu-alloy joints, where a compliant OFHC-Cu with different thickness was used as an interlayer, was carried out by using finite element method (FEM) under various conditions including the fabrication process and steady and transient operation.