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
August 2026
Nuclear Technology
July 2026
Fusion Science and Technology
Latest News
Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
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.