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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
Fusion Science and Technology
Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Jacob P. Gorton, Nicolas R. Brown (Penn State), Soon Kyu Lee, Yonho Lee (Univ of New Mexico)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1022-1027
We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.