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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Volkan Seker, Haining Zhou, Thomas J. Downar
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 805-824
Technical Paper | doi.org/10.1080/00295450.2019.1703464
Articles are hosted by Taylor and Francis Online.
The Transient Reactor Test Facility (TREAT) was designed in the late 1950s to test nuclear fuels and materials under extreme conditions and has been recently restarted by the U.S. Department of Energy to provide the transient test capability to evaluate the performance of innovative nuclear fuels under accident conditions. Benchmark experiment data are required to support the operation of TREAT and to validate the computational analyses necessary to design and evaluate the experiments. Therefore, in this paper, benchmark problems based on the minimum critical (MC) core and M8 Power Calibration Experiment (M8CAL) core of TREAT were developed and analyzed using the Monte Carlo code Serpent. The eigenvalue, temperature coefficient, and flux distributions for both the MC core and the M8CAL cores were calculated and compared to the experimental data. All the calculated values compared well to the experimental data, and both problems were subsequently approved as International Reactor Physics Experiment Evaluation Project benchmarks.