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.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Peter H. Titus, Matteo Salvetti
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 163-168
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A327
Articles are hosted by Taylor and Francis Online.
All three burning plasma experiments discussed at Snowmass during the summer of 2002, use preloaded structures to resist some component of the operating loads. For the resistive pulsed reactors, it is the preloads which introduce the most noticeable creep responses because these loads are applied for much longer than the operating loads. If the preloads are maintained during shut-down and maintenance periods, then the structure experiences the preload stresses at room temperature. OFHC copper has significant creep behavior, predominantly at high stress and high temp, but copper experiences finite creep even at cryogenic temperatures. The Beryllium copper used in the FIRE inner leg has better creep properties than OFHC copper.The purpose of these analyses is to characterize the influence of creep on the magnets of the Fusion Ignition Research Reactor (FIRE) and compare it with the creep response of the other proposed burning plasma experiments. The concern is that the desirable features provided by coil preloads will be lost over the lives of the experiments. Structural finite element models of FIRE and IGNITOR are used with creep equations derived from NIST[6] data to explore the structural sensitivity of the machines to creep. For both FIRE and IGNITOR, copper coil material, creep has been found to have a minimal effect on magnet performance. IGNITOR's generally lower stresses (with respect to FIRE's BeCu TF stresses) and the use of active as well as passive preload systems helps reduce creep to acceptable levels. FIRE's structure is more sensitive to creep due to the free standing wedged TF coil, but the BeCu used in FIRE's inner TF legs has a much lower creep behavior than ETP or OFHC copper. This reduces creep to acceptable levels. For FIRE, however, there is some creep in the horizontal legs which relaxes some of the support of the inner leg. Recommendations are presented to support the OFHC copper horizontal legs more effectively. More work is needed to address the multiple load-unload cycling effects on creep.