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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
Y. J. Chung, S. H. Yang, H. K. Kim, M. K. Chung, K. K. Kim
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 32-42
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4060
Articles are hosted by Taylor and Francis Online.
An experiment on a heat transfer and a natural-circulation performance for an integral-type reactor have been carried out using the VISTA facility, and the calculated results using the TASS/SMR and MARS codes have been compared with the experimental results. The VISTA is an experimental facility that consists of a primary system, a secondary system, and a passive residual heat removal system (PRHRS), to simulate the SMART (SysteM integrated modular Advanced ReacTor) plant. The experimental results show that the fluid is stabilized well in the primary system and the PRHRS under natural-circulation conditions. The TASS/SMR and MARS codes predict the overall characteristics of the natural circulation in the primary system and the PRHRS well. From the calculation results, most of the heat transferred from the primary system is removed at the PRHRS heat exchanger by a condensation heat transfer. Under natural-circulation conditions in the integral reactor, a smoothing function at the transition region between different heat transfer modes will be adopted in the TASS/SMR code and a pressure-loss model needs to be improved on the cross-flow bundle geometry in the MARS code.