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.
R. Nijsing, W. Eifler
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 289-299
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32329
Articles are hosted by Taylor and Francis Online.
The present version, THARC-S, of the transient thermohydraulic subassembly code, THARC, under development at the Joint Research Centre at Ispra, has been applied to predict the transient thermohydraulic behavior of liquid-metal fast breeder reactor subassemblies subjected to loss-of-flow conditions. Information is given on the present status of development of THARC. Computational results are presented for 217-rod subassemblies, both for grid and wire spacers. It is shown that radial power gradients and overcooling in the region adjacent to the wrapper wall cause boiling inception in the subassembly to be incoherent with, as a consequence, a more gradual boiling and voiding process than expected on the basis of a one-dimensional approach. It is demonstrated that heat capacity effects associated with the fuel rods and the wrapper wall are of considerable importance. Aspects associated with code validation in out-of-pile bundle experiments are also briefly discussed.